development of novel method for rapid extract of

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The Pennsylvania State University The Graduate School College of Engineering Development of Novel Method for Rapid Extract of Radionuclides from Solution Using Polymer Ligand Film A Dissertation in Nuclear Engineering by Jung H. Rim 2013 Jung H. Rim Submitted in Partial Fulfillment of the Requirements for the Degree of Doctor of Philosophy December 2013

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Page 1: Development of Novel Method for Rapid Extract of

The Pennsylvania State University

The Graduate School

College of Engineering

Development of Novel Method for Rapid Extract of

Radionuclides from Solution Using Polymer Ligand Film

A Dissertation in

Nuclear Engineering

by

Jung H. Rim

2013 Jung H. Rim

Submitted in Partial Fulfillment of the Requirements

for the Degree of

Doctor of Philosophy

December 2013

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ii

The dissertation of Jung H. Rim was reviewed and approved by the following: Kenan Ünlü Professor of Nuclear Engineering, Director of Radiation Science and Engineering Center Dissertation Advisor Chair of Committee Dominic S. Peterson Deputy Group Leader, MST-7 Polymers and Coatings Los Alamos National Laboratory Special Member Jack S. Brenizer Jr. J. ‘Lee’ Everett Professor of Mechanical and Nuclear Engineering Igor Jovanovic Associate Professor of Nuclear Engineering Bashore Faculty Development Professorship

Dan Sykes Senior Lecturer and Director, Analytical Instructional Laboratories Stephen LaMont Chief Scientist, Nuclear Materials Information Program Los Alamos National Laboratory Special Member Arthur Motta Chair of Nuclear Engineering Professor of Nuclear Engineering and Materials Science and Engineering *Signatures are on file in the Graduate School

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Abstract

Accurate and fast determination of the activity of radionuclides in a sample is

critical for nuclear forensics and emergency response. Radioanalytical techniques are

well established for radionuclides measurement, however, they are slow and labor

intensive, requiring extensive radiochemical separations and purification prior to

analysis. With these limitations of current methods, there is great interest for a new

technique to rapidly process samples. This dissertation describes a new analyte extraction

medium called Polymer Ligand Film (PLF) developed to rapidly extract radionuclides.

Polymer Ligand Film is a polymer medium with ligands incorporated in its matrix that

selectively and rapidly extract analytes from a solution. The main focus of the new

technique is to shorten and simplify the procedure necessary to chemically isolate

radionuclides for determination by alpha spectrometry or beta counting.

Five different ligands were tested for plutonium extraction: bis(2-ethylhexyl)

methanediphosphonic acid (H2DEH[MDP]), di(2-ethyl hexyl) phosphoric acid (HDEHP),

trialkyl methylammonium chloride (Aliquat-336), 4,4'(5')-di-t-butylcyclohexano 18-

crown-6 (DtBuCH18C6), and 2-ethylhexyl 2-ethylhexylphosphonic acid (HEH[EHP]).

The ligands that were effective for plutonium extraction further studied for uranium

extraction. The two ligands, H2DEH[MDP] and HDEHP, which showed effectiveness in

plutonium extraction were extensively studied. The extraction of strontium was

exclusively studied with DtBuCH18C6. This particular ligand was effective for strontium

separation in resin bead form. However, in PLF form, the ligand became completely

ineffective for strontium extraction.

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The plutonium recovery by PLFs has shown dependency on nitric acid

concentration and ligand to total mass ratio. H2DEH[MDP] PLFs performed best with

1:10 and 1:20 ratio PLFs. 50.44% and 47.61% of plutonium were extracted on the surface

of PLFs with 1M nitric acid for 1:10 and 1:20 PLF, respectively. HDEHP PLF provided

the best combination of alpha spectroscopy resolution and plutonium recovery with 1:5

PLF when used with 0.1M nitric acid. The overall analyte recovery was lower than

electrodeposited samples, which typically has recovery above 80%. However, PLF is

designed to be a rapid field deployable screening technique and consistency is more

important than recovery. PLFs were also tested using blind quality control samples and

the activities were accurately measured. It is important to point out that PLFs were

consistently susceptible to analytes penetrating and depositing below the surface. The

internal radiation within the body of PLF is mostly contained and did not cause excessive

self-attenuation and peak broadening in alpha spectroscopy. The analyte penetration issue

was beneficial in the destructive analysis. The extra plutonium contained in the PLF body

gave additional signal in the analysis. Plutonium was successfully back-extracted from

PLF and procedures were established for isotopic analysis by thermal ionization mass

spectrometry (TIMS). H2DEH[MDP] PLFs showed few advantages over HDEHP PLFs.

H2DEH[MDP] PLFs showed better sample recovery consistency than HDEHP. The

sample to sample variation in plutonium recovery was comparable to variation observed

with electrodeposited samples. H2DEH[MDP] PLF was also capable of co-extracting or

selectively extracting plutonium over uranium depending on the PLF composition. With

1:5 H2DEH[MDP] PLF, about 23% of plutonium and 20% uranium were co-extracted.

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On the other hand, both 1:10 and 1:20 PLFs were preferably extracting plutonium over

uranium at the same condition.

H2DEH[MDP] PLF was tested with environmental samples to fully understand

the capabilities and limitations of the PLF in relevant environments. The extraction

system was very effective in extracting plutonium from environmental water collected

from Mortandad Canyon at Los Alamos National Laboratory with minimal sample

processing. Soil samples were tougher to process than the water samples. Analytes were

first leached from the soil matrixes using nitric acid before processing with PLF. This

approach had a limitation in extracting plutonium using PLF. The soil samples from

Mortandad Canyon, which are about 1% iron by weight, were effectively processed with

the PLF system. Only 5.11x10-3% of iron from soil was leached using 1M nitric acid. The

Rocky Flats soils with higher iron content (2.6%) were unsuccessfully processed with

PLF for plutonium extraction. The leached solutions from the soil with higher iron

concentration had dark reddish color, which indicates a presence of large concentration of

iron. The large amount of iron in leached solution interfered and rendered PLF ineffective

for analyte extraction. No detectable activities were measured from Rocky Flats samples

processed with PLFs.

Even with certain limitations of the PLF extraction system, this technique was

able to considerably decrease the sample analysis time. The entire environmental sample

was analyzed within one to two days. The decrease in time can be attributed to the fact

that PLF is replacing column chromatography and electrodeposition with a single step for

preparing alpha spectrometry samples. The two-step process of column chromatography

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and electrodeposition takes a couple days to a week to complete depending on the

sample. The decrease in time and the simplified procedure make this technique a unique

solution for application to nuclear forensics and emergency response. A large number of

samples can be quickly analyzed and selective samples can be further analyzed with more

sensitive techniques based on the initial data. A procedure was established to perform

TIMS analysis and plutonium isotopics were measured in a number of PLF samples. The

deployment of a PLF system as a screening method will greatly reduce a total analysis

time required to gain meaningful isotopic data for the nuclear forensics application.

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TABLE OF CONTENTS

LIST OF FIGURES ..................................................................................................... x

LIST OF TABLES ....................................................................................................... xvi

ACKNOWLEDGEMENTS ......................................................................................... xviii

Chapter 1 Introduction ................................................................................................ 1

Chapter 2 Polymer Ligand Film Preparation .............................................................. 5

2.1 Introduction ..................................................................................................... 5 2.2 Background: Polymer Thin Film Deposition Techniques .............................. 5

2.2.1 Solvent Casting ..................................................................................... 5 2.2.2 Spin Coating ......................................................................................... 7 2.2.3 Spray Coating ....................................................................................... 9 2.2.4 Chemical Vapor Deposition ................................................................. 10 2.2.5 Pulsed Laser Deposition ....................................................................... 12 2.2.6 PLF Preparation Method Selection ...................................................... 13

2.3 PLF Preparation Experiment .......................................................................... 15 2.3.1 PLF Stock Solution ............................................................................... 15 2.3.2 Solvent Casting Method ....................................................................... 19 2.3.3 Nebulizer Spraying Coating Method .................................................... 22 2.3.4 Spin Coating Method ............................................................................ 24

2.4 PLF Preparation Conclusions ......................................................................... 26

Chapter 3 Bis(2-ethylhexyl) methanediphosphonic acid (H2DEH[MDP]) ................ 28

3.1 Introduction ..................................................................................................... 28 3.2 Theory and Background ................................................................................. 28 3.3 Plutonium and Uranium Extraction ................................................................ 31

3.3.1 Analyte Extraction Characterization .................................................... 32 3.3.2 Time Dependency Test ......................................................................... 42 3.3.3 Consistency Study ................................................................................ 45 3.3.4 Blind Study ........................................................................................... 49 3.3.5 Alternate PLFs ...................................................................................... 50

3.4 Digital Autoradiography ................................................................................. 52 3.5 Uranium Analysis ........................................................................................... 54 3.6 Mass Spectroscopy Analysis .......................................................................... 56

3.6.1 Back-extraction with Nitric Acid and Deionized Water ...................... 58 3.6.2 Back-extraction with Isopropanol ........................................................ 60 3.6.3 TIMS Analysis ...................................................................................... 61

3.7 H2DEH[MDP] PLF Conclusions .................................................................... 67

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Chapter 4 Di(2-ethylhexyl) phosphoric acid (HDEHP).............................................. 69

4.1 Introduction ..................................................................................................... 69 4.2 Theory and Background ................................................................................. 69 4.3 Plutonium and Uranium Extraction ................................................................ 72

4.3.1 Analyte Extraction Characterization .................................................... 73 4.3.2 Analyte Extraction Time Dependency ................................................. 80 4.3.3 Consistency Study ................................................................................ 82 4.3.4 Alternate PLFs ...................................................................................... 89

4.4 Surface Characterization ................................................................................. 90 4.5 Uranium Analysis ........................................................................................... 93 4.6 Mass Spectroscopy Analysis .......................................................................... 94

4.6.1 Back-extraction with Nitric Acid and Deionized Water ...................... 95 4.6.2 Back-extraction with Isopropanol ........................................................ 96 4.6.3 TIMS Analysis ...................................................................................... 97

4.7 HDEHP PLF Analysis Conclusions ............................................................... 99

Chapter 5 Other Ligands ............................................................................................. 101

5.1 Trialkyl methylammonium chloride (Aliquat-336) ........................................ 101 5.1.1 PLF Preparation and Testing ................................................................ 103

5.2 4,4’,(5’)-di-(tert-butylcyclohexano)-18-crown-6 (DtBuCH18C6) ................. 104 5.2.1 Plutonium Extraction ............................................................................ 106 5.2.2 Strontium Extraction ............................................................................ 109

5.3 2-ethylhexyl 2-ethylhexylphosphonic acid (HEH[EHP]) ............................... 111 5.3.1 Plutonium Extraction ............................................................................ 114

Chapter 6 Environmental Sample Analysis ................................................................ 118

6.1 Soil Sample Analysis ...................................................................................... 119 6.1.1 Soil Characterization ............................................................................ 119 6.1.2 Mortandad Canyon Soil Leaching Study ............................................. 122 6.1.3 Rock Flats Soil Leaching Study ........................................................... 127

6.2 Water Sample Analysis................................................................................... 132 6.2.1 Environmental Water Characterization ................................................ 132 6.2.2 Environmental Water Processing with PLF ......................................... 133

6.3 Environmental Sample Analysis Conclusions ................................................ 135

Chapter 7 Summary and Conclusions ......................................................................... 137

7.1 Recommendations and Future Studies............................................................ 140

Appendix A Counting Software Code ........................................................................ 142

Appendix B H2DEH[MDP] PLF Plutonium Distribution Maps................................. 146

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Appendix C HDEHP PLF Plutonium Distribution Maps ........................................... 149

Appendix D Gamma Spectra from Mortandad Canyon Soil Samples ....................... 152

Bibliography ................................................................................................................ 154

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LIST OF FIGURES

Figure 1-1 Diagram comparing conventional sample preparation method and PLF method .................................................................................................................. 4

Figure 2-1 (A) Stationary solvent casting operation, (B) Continuous solvent casting using a belt system ................................................................................... 6

Figure 2-2 A graphical depiction of four stages in spin coating .................................. 7

Figure 2-3 Chemical vapor deposition setup .............................................................. 11

Figure 2-4 Pulsed laser deposition setup ..................................................................... 12

Figure 2-5 PLF stock solution (A) with un-dissolved polystyrene, (B) with polystyrene completely dissolved ......................................................................... 18

Figure 2-6 PLFs prepared with solvent casting method .............................................. 20

Figure 2-7 Crown ether PLFs with large population of bubbles along the edge ......... 20

Figure 2-8 A Latex and Nitrile substrates damaged by THF ....................................... 22

Figure 2-9 Nebulizer setup for PLF spraying .............................................................. 22

Figure 2-10 Nebulizer spray coating setup .................................................................. 23

Figure 2-11 Sprayed PLF (A) before heat treatment (B) after heat treatment ............. 24

Figure 2-12 Uneven polymer film coating on stainless steel substrates by spin coating method ...................................................................................................... 25

Figure 2-13 PLF spin coating setup ............................................................................. 25

Figure 3-1 Chemical structure of H2DEH[MDP] ........................................................ 29

Figure 3-2 Alkaline earth metal extraction mechanism with H2DEH[MDP] .............. 30

Figure 3-3 H2DEH[MDP] distribution ratio dependency on HCl concentration for various ions ........................................................................................................... 31

Figure 3-4 Alpha spectroscopy sample tray (A) before modification (B) after modification .......................................................................................................... 33

Figure 3-5 The baseline performance of H2DEH[MDP] PLF in plutonium extraction as a function of nitric acid concentration ............................................. 34

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Figure 3-6 Plutonium recovery by 1:10 through 1:20 H2DEH[MDP] PLF as a function of nitric acid concentration ..................................................................... 35

Figure 3-7 1:25 H2DEH[MDP] PLF with damaged surface ....................................... 36

Figure 3-8 Unaccounted plutonium by H2DEH[MDP] PLF as function of nitric acid concentration ................................................................................................. 37

Figure 3-9 Unaccounted plutonium activity with 8M nitric acid ................................ 38

Figure 3-10 Plutonium penetration mechanism experiment by varying tracer solution volumes ................................................................................................... 39

Figure 3-11 Schematic diagram of PLF analyte extraction mechanism ...................... 40

Figure 3-12 H2DEH[MDP] PLF plutonium recovery at different exposure time ....... 43

Figure 3-13 H2DEH[MDP] PLFs from two batches ................................................... 47

Figure 3-14 Plutonium recoveries by two different batch 1:20 H2DEH[MDP] PLFs with 0.1M nitric acid solution ..................................................................... 47

Figure 3-15 Digital autoradiography image from 1:20 H2DEH[MDP] PLF ............. 53

Figure 3-16 Plutonium distribution maps of H2DEH[MDP] PLF generated from digital autoradiography image .............................................................................. 54

Figure 3-17 Uranium recovery by H2DEH[MDP] PLF as function of nitric acid concentration ......................................................................................................... 55

Figure 3-18 H2DEH[MDP] PLF Pu and U extraction efficiency with 1M nitric acid ........................................................................................................................ 56

Figure 3-19 (A) TIMS turret with triple-filament (B) TIMS sample turret in chamber ................................................................................................................. 62

Figure 3-20 Comparison of TIMS 240/239Pu isotopic ratio measurements from back-extracted samples and known values ........................................................... 63

Figure 3-21 Illustration of PLF direct sample mounting on TIMS filament ............... 64

Figure 3-22 TIMS filament prepared with (A) ligand-polymer method (B) ligand complex method .................................................................................................... 65

Figure 3-23 TIMS spectrum from 242Pu sample prepared by ligand-polymer method .................................................................................................................. 66

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Figure 4-1 Chemical structure of HDEHP ................................................................... 69

Figure 4-2 HDEHP distribution ratio dependency on HNO3 concentration for various ions [50] ................................................................................................... 72

Figure 4-3 HDEHP ligand based PLFs ........................................................................ 73

Figure 4-4 The baseline performance of HDEHP PLF in plutonium extraction as a function of nitric acid concentration ..................................................................... 74

Figure 4-5 Alpha spectra for 1:2 (blue) and 1:5 (red) PLFs ........................................ 76

Figure 4-6 Plutonium recovery by 1:6 through 1:20 HDEHP PLF as a function of nitric acid concentration ....................................................................................... 78

Figure 4-7 Plutonium recovery by 1:2 through 1:5 HDEHP PLF as a function of nitric acid concentration ....................................................................................... 78

Figure 4-8 Plutonium recovery by HDEHP PLF as function of PLF composition ..... 79

Figure 4-9 Unaccounted plutonium by H2DEH[MDP] PLF as function of nitric acid concentration ................................................................................................. 80

Figure 4-10 HDEHP and H2DEH[MDP] PLF plutonium recoveries at different exposure time ........................................................................................................ 81

Figure 4-11 Plutonium recoveries by 1:5 HDEHP PLFs with 0.1M nitric acid solution ................................................................................................................. 84

Figure 4-12 Comparison of two HDEHP PLF batches after alpha counting ............... 85

Figure 4-13 1:5 HDEHP PLF (A) after heat treatment (B) after 16 day outgassing ... 86

Figure 4-14 Alpha spectra comparison between heat treated HDEHP PLF (blue) and air dried PLF (red) ......................................................................................... 87

Figure 4-15 1:5 HDEHP PLF surface color progression over 12 days ....................... 88

Figure 4-16 Heat treated 1:5 HDEHP PLF surface color progression over 12 days ... 89

Figure 4-17 Alpha spectra comparison between for heat treated 1:5 HDEHP and regular PLFs .......................................................................................................... 90

Figure 4-18 SEM images for different ratio HDEHP PLFs ......................................... 91

Figure 4-19 Digital autoradiography image of 1:2 and 1:5 HDEHP PLFs.................. 92

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Figure 4-20 Plutonium distribution map of HDEHP PLF generated from digital autoradiography image ......................................................................................... 93

Figure 4-21 Uranium recovery by HDEHP PLF as function of nitric acid concentration ......................................................................................................... 94

Figure 4-22 Comparison of TIMS 239/240Pu isotopic ratio measurements from back-extracted samples and known values ........................................................... 98

Figure 5-1 Chemical structure of Aliquat-336 ............................................................. 101

Figure 5-2 Aliquot-336 distribution ratio dependency on HNO3 concentration for various ions ........................................................................................................... 102

Figure 5-3 Aliquat-336 PLF damaged by high concentration nitric acid .................... 104

Figure 5-4 Strontium 18-crown-6 complex ................................................................. 105

Figure 5-5 Chemical structure of (A) DC18C6 (B) DtBuCH18C6 ............................. 105

Figure 5-6 DtBuCH18C6 distribution ratio dependency on HNO3 concentration for various ions ..................................................................................................... 106

Figure 5-7 Crown ether PLFs prepared with solvent casting method ......................... 107

Figure 5-8 Plutonium recovery by crown ether PLF as a function of nitric acid concentration ......................................................................................................... 108

Figure 5-9 Unaccounted plutonium recovery by crown ether as a function of nitric acid concentration ................................................................................................. 108

Figure 5-10 Crown ether PLFs damaged by high concentrated nitric acid ................. 109

Figure 5-11 Crown ether PLF coated LSC vial diagram ............................................. 110

Figure 5-12 Chemical structure of HEH[EHP] ............................................................ 112

Figure 5-13 HEH[EHP] distribution ratio dependency on HNO3 concentration for various ions ........................................................................................................... 113

Figure 5-14 HEH[EHP] distribution ratio relative to HDEHP [79] ............................ 114

Figure 5-15 Plutonium recovery by HEH[EHP] PLF as a function of nitric acid concentration ......................................................................................................... 115

Figure 5-16 Unaccounted plutonium recovery by HEH[EHP] as a function of nitric acid concentration ....................................................................................... 116

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Figure 6-1 Mortandad Canyon soil samples ................................................................ 119

Figure 6-2 Fusion sample (A) before (B) after processing with the muffle furnace ... 122

Figure 6-3 Leached solution (A) before (B) after syringe filtering ............................. 123

Figure 6-4 Plutonium leaching dependency on the nitric acid concentration .............. 125

Figure 6-5 Plutonium leaching dependency on time for 1M ntiric acid and white distilled vinegar .................................................................................................... 126

Figure 6-6 239+240Pu extracted with 1:20 H2DEH[MDP] PLF at different leaching and exposure time ................................................................................................. 127

Figure 6-7 Rocky Flats soil leaching with vinegar or various concentration nitric acid solutions ........................................................................................................ 129

Figure 6-8 Rocky Flats soil leached solutions after syringe filtering .......................... 129

Figure 6-9 Residue left on beaker after leached nitric acid was dried ......................... 131

Figure 6-10 Rocky Flats leached solution stippled on 1:20 H2DEH[MDP] PLFs ...... 131

Figure B-1 Plutonium distribution maps of H2DEH[MDP] PLF generated from digital autoradiography image (sample ID: 095JR2A) ......................................... 146

Figure B-2 Plutonium distribution maps of H2DEH[MDP] PLF generated from digital autoradiography image (sample ID: 095JR2B) ......................................... 146

Figure B-3 Plutonium distribution maps of H2DEH[MDP] PLF generated from digital autoradiography image (sample ID: 095JR2C) ......................................... 147

Figure B-4 Plutonium distribution maps of H2DEH[MDP] PLF generated from digital autoradiography image (sample ID: 095JR2D) ......................................... 147

Figure B-5 Plutonium distribution maps of H2DEH[MDP] PLF generated from digital autoradiography image (sample ID: 095JR2G) ......................................... 147

Figure B-6 Plutonium distribution maps of H2DEH[MDP] PLF generated from digital autoradiography image (sample ID: 095JR2H) ......................................... 148

Figure B-7 Plutonium distribution maps of H2DEH[MDP] PLF generated from digital autoradiography image (sample ID: 095JR2I) .......................................... 148

Figure B-8 Plutonium distribution maps of H2DEH[MDP] PLF generated from digital autoradiography image (sample ID: 095JR2J) .......................................... 148

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Figure C-1 Plutonium distribution map of 1:2 HDEHP PLF generated from digital autoradiography image (sample ID: 043JR2A) .................................................... 149

Figure C-2 Plutonium distribution map of 1:2 HDEHP PLF generated from digital autoradiography image (sample ID: 043JR2B) .................................................... 149

Figure C-3 Plutonium distribution map of 1:2 HDEHP PLF generated from digital autoradiography image (sample ID: 043JR2C) .................................................... 150

Figure C-4 Plutonium distribution map of 1:5 HDEHP PLF generated from digital autoradiography image (sample ID: 043JR2D) .................................................... 150

Figure C-5 Plutonium distribution map of 1:5 HDEHP PLF generated from digital autoradiography image (sample ID: 043JR2E) .................................................... 150

Figure C-6 Plutonium distribution map of 1:5 HDEHP PLF generated from digital autoradiography image (sample ID: 043JR2F) ..................................................... 151

Figure D-1 Gamma spectrum from Mortandad Canyon soil sample (sample ID: 149JR2A) .............................................................................................................. 152

Figure D-2 Gamma spectrum from Mortandad Canyon soil sample (sample ID: 149JR2B) .............................................................................................................. 153

Figure D-3 Gamma spectrum from Mortandad Canyon soil sample (sample ID: 149JR2C) .............................................................................................................. 153

Figure D-4 Gamma spectrum from Mortandad Canyon soil sample (sample ID: 149JR2D) .............................................................................................................. 153

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LIST OF TABLES

Table 2-1 Advantages and disadvantages of each thin film technique ........................ 14

Table 2-2 Commonly used solvents to dissolve polymers ........................................... 17

Table 2-3 Polystyrene and Tetrahydrofuran properties ............................................... 18

Table 3-1 Plutonium penetration dependency on solution volume ............................. 40

Table 3-2 Average FWHM and Tailing for H2DEH[MDP] PLFs tested for plutonium extraction ............................................................................................. 42

Table 3-3 Plutonium activities per 100 fg of analyte ................................................... 45

Table 3-4 Mass of components used to prepare two H2DEH[MDP] PLF batches for the consistency study ...................................................................................... 46

Table 3-5 Average plutonium recovery by each batch ................................................ 48

Table 3-6 Plutonium activity measurements from blind samples using 1:20 H2DEH[MDP] PLF .............................................................................................. 49

Table 3-7 Uranium tracer activity information ............................................................ 55

Table 3-8 Plutonium back-extraction with nitric acid and DI water ........................... 59

Table 3-9 Plutonium back-extracted from H2DEH[MDP] PLF using isopropanol ..... 61

Table 3-10 240/239Pu isotopic ratio for each samples .................................................... 62

Table 3-11 Information of plutonium standards used in TIMS analysis ..................... 66

Table 4-1 Alpha spectra resolutions and tailing terms for HDEHP PLFs ................... 75

Table 4-2 Mass of components used to prepare two HDEHP PLF batches for consistency study .................................................................................................. 83

Table 4-3 Average plutonium recovery by HDEHP PLF batches ............................... 84

Table 4-4 Plutonium recovery improvement after outgassing and heat treatment ...... 86

Table 4-5 HDEHP PLF plutonium back-extraction with nitric acid and DI water ..... 95

Table 4-6 HDEHP PLF plutonium back-extraction with isopropanol......................... 97

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Table 6-1 Mortandad Canyon soil radionuclide activities measured with HPGe ........ 120

Table 6-2 Elemental information gained from NAA ................................................... 121

Table 6-3 Elements leached from Mortandad Canyon soil using nitric acid ............... 124

Table 6-4 Rocky Flats standard soil certified radionuclide activities .......................... 128

Table 6-5 239+240Pu leached activities from Rock Flats soil and percent activity recoveries based on certified values ..................................................................... 130

Table 6-6 Elemental composition of Rocky Flats SRM .............................................. 132

Table 6-7 Simulated environmental water sample plutonium recoveries .................... 134

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ACKNOWLEDGEMENTS

I would like to thank my Dissertation Advisor, Dr. Kenan Ünlü, for his advice and

the support for this research. His guidance was instrumental in completion of this study. I

would like to also sincerely appreciate my laboratory mentor, Dr. Dominic Peterson, for

providing me with an opportunity to conduct research at the Los Alamos National

Laboratory. It was truly a valuable experience that I have had and will never forget all the

expert guidance that was given to me. In addition, I would not have been able to complete

my work without the help from the Claudine Armenta and Edward Gonzales. Dr. Stephen

LaMont was also essential in completing this study. I also would like to show my

gratitude to staffs at the Penn State Radiation Science & Engineering Center for their

support. Finally, I would like to thank my family, Miel and Aleena, for all their patience

and support.

This research was performed under the Nuclear Forensics Graduate Fellowship

Program which is sponsored by the U.S. Department of Homeland Security’s Domestic

Nuclear Detection Office and the U.S. Department of Defense’s Defense Threat

Reduction Agency. Los Alamos National Laboratory is operated by Los Alamos National

Security, LLC for the U.S. Department of Energy under contract number DE-AC52-

06NA25396. This document had been reviewed and assigned publication number: LA-

UR-13-26848 Version 3.

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1. Chapter 1

Introduction

The goal of this research was to develop a novel method to selectively extract

uranium, plutonium, and strontium from a solution using Polymer Ligand Films (PLF) to

assist with generating rapid data during nuclear forensics investigations. This new

radioanalytical technique showed a great potential to be deployed during a nuclear

emergency as a way to deliver fast and reliable nuclear forensics or consequence

management data. High sample throughput is critical in an emergency response since

there is a potential need to analyze an enormous number of samples in a short time.

Current radioanalytical techniques are quite mature and well established for the analysis

of many radionuclides of interest. However, these are not well suited for rapid analysis or

pre-screening of samples to determine which might be the best suited for performing a

more accurate but time consuming set of analyses. Also, these classical methods require a

fully functional chemistry laboratory to process the samples, which greatly limits the

possibility of field analysis. These limitations of classical procedures greatly hinder the

ability to accurately assess and respond to an incident in a prompt manner.

A PLF is a thin polymer medium with ligands incorporated on to its structure to

enable selective extraction of analytes from a solution. PLFs developed in this research

were designed to use as a fast screening method for radionuclide measurement. The main

focus will be to shorten and simplify the procedure for chemically processing samples

and preparing them for radiometric counting. To achieve this goal, PLFs were

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synthesized to separate anlaytes directly from solution onto a surface suitable for

radiometric counting techniques, such as alpha, beta, and gamma spectroscopy.

Several authors have reported the possibility of extracting both radioactive and

non-radioactive analytes using thin film substrates [1]–[7]. The thin film extraction

technique is similar to a resin based extraction with an added benefit of easier path

forward for radiometric analysis. Koulouridakis et al. were successful in selectively

extracting mercury from a large volume solution using a membrane with 24 hours of

equilibration time. The active components of the membrane were poly(vinylchloride),

dibutyl phthalate plasticizer, tetrahydrofuran, and DTBNBA [1]. Surbeck has reported the

possibility of using 400 mm2 MnO2 thin film to effectively extract radium from a water

sample with six-hour exposure time [2]. MnO2 films were directly counted with alpha

spectroscopy and showed similar energy resolution as electrodeposited sources. Surbeck

also has used commercially available resin beads to prepare thin films for uranium

extraction. The films were prepared from finely ground resin beads, and the fine powder

was fixed onto a flat surface. Fifty percent of uranium was recovered within 4 hours, and

80% was extracted in about 20 hours [2]. The alpha spectroscopy peak resolution was not

as good as the electrodeposited samples; probably due to the unevenness of the film

surface. Wang et al. used a 54 mm2 Aliquat-366/PVC liquid membrane system to extract

Cd(II) from HCl solution [7]. The membrane was prepared by dissolving Aliquat-366 and

PVC in THF then poured into a mold. Gonzales et al. have used Bis(2-ethylhexyl)

methanediphosphonic acid based thin film for plutonium and americium separation from

the solution with a 2 hour collection time [4]. The thin film was synthesized by dissolving

ligand and poly(styrene) in THF. Gonzales et al. have also applied their technique to

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environmental samples. Extraction efficiency and alpha spectrum resolution showed

dependency on the solution and surface chemistry [3], [4].

All reviewed literature demonstrated the effectiveness of utilizing thin films for

extraction of analytes in a solution. These studies have shown that extraction efficiencies

are greatly influenced by ligands used in the film. Also, the alpha spectroscopy resolution

is dependent on surface structure. The most important characteristic to consider a ligand

is its ability to extract analytes from the solution. The second characteristic to consider is

how strongly the ligand forms a complex with analytes. It is important to have a stable

complex to ensure that radionuclides are not discharged during extensive non-destructive

analysis.

Polymer Ligand Film is a thin polymer medium with ligands incorporated onto its

structure to enable selective extraction of analytes from a solution. PLFs developed in

this research were designed to facilitate the fast isolation of radionuclides from solutions

for screening samples. The main focus was to shorten and simplify the procedure for

separating radionuclides from solutions onto a surface appropriate for radiometric

counting. To achieve this goal, PLFs were synthesized to perform direct sorption of

analytes onto its surface for direct counting using radiometric techniques, such as alpha

and beta spectroscopy. A diagram comparing the classical method and PLF technique is

shown in Figure 1-1. The new technique combined column chromatography and

electrodeposition into a single step for alpha ray emitting samples.

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Figure 1-1 Diagram comparing conventional sample preparation method and PLF method

PLFs were examined for plutonium, uranium, and strontium extraction. Plutonium

and uranium have always been the most important elements in nuclear forensics and

incident response due to their potential use in nuclear weapons. Isotopic ratio data for

these elements provides crucial information for identifying the origin and the intended

use of the material. The two most important uranium isotopes are 235U and 238U, which

can be determined with alpha spectroscopy. Plutonium is a man-made element with at

least 15 different radioactive isotopes. Alpha decay is the most common form of decay

for plutonium isotopes. The 240Pu/239Pu isotopic ratio provides the most important

forensic information. The origin and intended use of the material can be gathered from

the plutonium isotopic ratio. However, unlike uranium, the conventional alpha

spectroscopy is not capable of making this isotopic measurement due to similar energy of

alpha particles emitted by 239Pu and 240Pu. Mass spectrometry is the only reliable

measurement technique capable of accurately measuring the 240Pu/239Pu isotope ratio.

PLF was designed mainly for radiometry techniques but plutonium can be extracted out

of the PLF for further analysis including mass spectrometry to determine the 240Pu/239Pu

ratio.

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2. Chapter 2

Polymer Ligand Film Preparation

2.1 Introduction

Several thin film preparation methods were investigated for Polymer Ligand Film

(PLF) preparation. Each technique was evaluated for practicality and consistency in

synthesizing PLF. Three techniques were selected and used to prepare PLFs. All three

methods used a solvent to dissolve ligand and polystyrene into a solution. Each of three

components, ligand, polystyrene, and solvent, has unique role and is equally important in

generating the PLF. Each component was carefully evaluated to select best combination

of materials.

2.2 Background: Polymer Thin Film Deposition Techniques

Polymer thin films can be prepared with several different deposition techniques.

Each of these techniques provides certain advantages and disadvantages. In this section,

these techniques are reviewed and compared for polymer thin film preparation.

2.2.1 Solvent Casting

Solvent casting is the oldest technology used to manufacture plastic films. This

technique is extremely simple to implement and produce uniform thickness film with a

maximum optical purity [8]. The polymer must be dissolved in a solvent before being

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used in this process. Dissolving a polymer in a solvent is a slow process. At first, solvent

molecules slowly diffuse into the polymer to produce a swollen gel. If polymer-solvent

interaction is stronger than the polymer-polymer intermolecular force, then the gel slowly

dissolves into the solvent [9], [10]. Once the polymer is completely dissolved in a

solvent, the solution is transferred into a cast to form a film. The polymer film is formed

once the solvent is completely evaporated. The film is then removed from the cast. The

commercial solvent casting is a continuous process, where moving belt is utilized to

continuously generate a film. This technique is used in the industrial production of

engineering plastics, films, and sheet forming for electronic applications [8]. Stationary

and continuous solvent casting process is shown in Figure 2-1.

Figure 2-1 (A) Stationary solvent casting operation, (B) Continuous solvent casting using a belt system

Solvent casting may affect the physical and mechanical properties of the polymer

[11]. The casting process also may affect the orientation of the polymeric chains. Solvent

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evaporation from a polymer film results in one-dimensional thickness reduction. The

orientation of the polymeric chains is determined by stretching the polymer in the planar

directions during the solvent evaporation process [11].

2.2.2 Spin Coating

Spin coating technique is widely utilized to produce thin and uniform films on the

flat substrates [12], [13]. It is a mature and cost effective technique that has been studied

extensively [14]. It has been reported that thin film thickness of 1-2 µm is routinely

prepared with this technique [13]. The technique uses centrifugal forces to spread

solution to thinly cover the entire substrate. There are four distinct stages in this process:

deposition, spin-up, spin-off, and finally evaporation [12]. Each step is illustrated

graphically in Figure 2-2.

Figure 2-2 A graphical depiction of four stages in spin coating

In the deposition step, the polymer solution is transferred to the flat substrate. The

solution can cover the entire surface or just deposited on the center of the surface. In the

spin-up step, the substrate is accelerated rapidly to a high angular velocity to radially

spread the polymer solution over the entire surface. Once the solution is spread over the

entire surface, excess mass is removed in the spin-off process. The process is similar to

the spin-up. It uses a high angular velocity to remove solution and leaves only thin

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polymer coating on a substrate. The last step in the spin coating method is evaporation. In

this step, solvent that may still be within the film evaporates. The thickness of the film

can slightly change based on the amount of solvent evaporated in this process [15].

The thickness of the film is mainly determined by the rotation speed, solvent

viscosity, and solvent volatility [12], [13], [15]. Generally a higher rotation speed

produces thinner polymer films. The greater the solution viscosity the slower the solution

spreads over the substrate. The total spin time and speed required to achieve the thickness

increases with the increase in viscosity. Equation 2.1 shows the relation of the film

thickness to viscosity and spin speed [16],

𝑡 ∝ �𝜇𝜔

Equation 2.1

where µ is viscosity and ω is spin speed. The viscosity of the polymer solution changes

during the spin-up and spin-off processes due to the evaporation of the solvent. Rapid

acceleration may be needed for the volatile solution to achieve the desired film thickness

[16]. One of the advantages of this technique is that once the film becomes completely

uniform during the coating process, it will remain for the duration of the process [14].

The two main disadvantages of spin coating are low efficiency and limitation on

substrate size. Typical spin coating only retains 2-5% of solution dispensed onto the

substrate [14]. The rest of the solution is spun off from the substrate during the coating

process. Also, the spin coating is not ideal for the large substrates. Large substrates need

to be spun at higher angular velocity than the smaller substrates to prepare thin films [14].

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At certain substrate size, the cost of the spin coater that can provide the required angular

speed start to become too costly.

2.2.3 Spray Coating

Polymer spray coating is a technique used to prepare thin coating on a substrate.

This technique can produce thin coating layer on irregular shaped objects at a very fast

rate [17]. Spray coating may involve liquids, gases, or solids depending on the polymer

used and the type of spray system used. The polymer can be dissolved in a suitable

solvent and this polymer solvent mixture can be used to produce a thin film using a spray

coating method. In liquid polymer system, the fluid is atomized into small droplets and

sprayed over the substrate [17], [18]. The polymer solution is forced through an orifice

and as it exits the opening, high pressure gas is used to atomize the solution [17]. A

device such as a nebulizer is routinely used for atomization purpose. The size of the

droplet exiting the orifice can be adjusted by changing solution viscosity, pressure, and

orifice size [17].

For the solid polymer, a thermal polymer spraying technique is used. As the name

implies, in thermal spraying, the polymer is melted with heat to a molten state or semi-

molten state. [18], [19]. The molten polymer is then blown through a flame shrouded

orifice by running compressed gas through the orifice [18]. The molten polymer particles

coalesce and flow to form a homogeneous coating on a substrate as it cools and dries

[19].

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Spray coating has several drawbacks. It is difficult to have precise control over

the coating area. The stream of polymer leaving the orifice may not cover the entire

substrate and multiple coatings have to be applied to cover the entire surface. During the

spraying operation, some area may be sprayed multiple times and leave an un-even

thickness. Another issue is the large amount of volatile organic compound emitted when

using solvent to dissolve the polymer. [17]

2.2.4 Chemical Vapor Deposition

Chemical vapor deposition (CVD) is a widely used technique to produce thin

coating on substrates [20]–[22]. The technique offers highly pure and extremely uniform

films even at large specimen [20]. It was first developed to prepare inorganic films but

the majority elements have been successfully processed with CVD [20]. In a typical

CVD, volatile precursors are introduced into a reactor and react with substrate that is

heated to 1000 oC. The reaction occurs on and near the substrate and produces a desired

thin film [20], [23], [24]. The conventional CVD process works well with inorganics,

which typically do not degrades under high temperature. However, this high temperature

is undesired for the polymer thin film process. The polymer function groups are damaged

due to the temperature and lead to unwanted crosslinking [24]. Unreacted precursors and

chemical by-products are evacuated through the exhaust in the reactor. The general CVD

setup is shown in Figure 2-3.

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Figure 2-3 Chemical vapor deposition setup

The limitation of conventional CVD is overcome by modifications to the reactants

and reactor designs [24]. In polymer CVD, vapor phase monomers are reacted to form a

pure polymer film on a substrate. One of the advantages of polymer CVD is that it can

prepare wide variety of polymers that are not typically possible with other methods. CVD

can prepare highly crosslinked insoluble polymers, conductive polymers, and copolymers

of incompatible monomers [24]. Also, the process is solventless and can be coated on

virtually any surface [23], [24]. The disadvantages of CVD are mostly related to safety

and chemical hazards. Precursors are generally toxic, corrosive, flammable, and/or

explosive [25]. Extra care must be taken to operate the system due to the precursor

toxicity.

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2.2.5 Pulsed Laser Deposition

Pulsed laser deposition (PLD) is a widely used technique to prepare inorganic thin

films. It is also possible to prepare certain polymer thin films without any modification

and a large range of polymer films can be prepare with slight modification to the

deposition system. A typical PLD system uses a high-power UV pulsed laser, such as

krypton fluoride excimer laser, to ablate material from surface. Once material is freed

from the target surface, it is collected on a heated sample substrate to form a thin film

[26], [27]. The photon energy emitted from the UV laser is high enough to break polymer

chains and change chemical and physical properties of the polymer material [28]. This

phenomenon can be used with certain polymers, such as PTFE, to prepare thin film [29],

[30]. Polymer is ablated in monomer form then subsequently re-polymerized on sample

substrate [31].

Figure 2-4 Pulsed laser deposition setup

The PLD technique can be modified by replacing UV laser with IR pulse laser to be more

favorable for polymer film preparation. With an IR laser, chemical structure of polymer

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is maintained during the ablation step and final product has the same property as the bulk

target material.

There are a few advantages of PLD over other techniques. It requires relatively

simple setup to prepare samples; a typical PLD setup is shown in Figure 2-4. The target

materials can be in many different solid forms, such as a powder, sintered pellets, and

single crystal [32], [33]. This technique is certainly not without limitations. The pulse

laser produces microscopic particles during the ablation process causing uneven

deposition [32], [34]. Further, the deposition area is limited to a few cm2 [34].

2.2.6 PLF Preparation Method Selection

The five methods discussed in the previous sections were carefully evaluated for

the PLF synthesis and the most suitable methods were selected. Each technique requires

vastly different sample preparation apparatus and procedures. The main advantages and

disadvantages of each polymer thin film technique are given in Table 2-1. The technique

must be easy to implement and result in minimal variation between sample to sample.

Table is generated to list pros and cons of each technique. A large number of samples

were needed to effectively test PLF for analyte extraction in varying conditions. It is

important that the PLF preparing method is cost effective and easy to scale up to provide

adequate supply of PLFs. Five methods can be categorized into two groups, solvent based

or solventless techniques.

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Table 2-1 Advantages and disadvantages of each thin film technique Technique Pros Cons Solvent casting Simple setup

Easy to scale up Use of volatile solvent Thick deposition

Spray coating Thin coating Odd size and shape

Use of volatile solvent Uneven deposition

Spin coating High purity Use of volatile solvent Limitation on deposition size

Chemical vapor deposition

Solventless Uniform deposition

Complex setup High cost equipment Safety issue Need highly pure compounds

Pulsed laser deposition

Solventless Target materials

High cost equipment Uneven deposition Limitation on deposition size

Solvent casting, spray coating, and spin coating are all solvent based techniques.

Solvent based techniques generally have limited choices of materials that can be used as a

backing plate due to use of volatile solvent. Solvent casting is the simplest technique to

implement for PLF preparation. It is also the best method to generate large number of

PLF required for the testing. Spray and spin coating methods are both capable of

producing thinner film but these need more complicated setups than solvent casting. With

spray coating, solvent evaporates instantaneously and does not damage substrates, which

allows this technique to be possibly used with multiple substrates that are normally

impossible with other techniques.

Chemical vapor deposition and pulsed laser deposition are both solventless

techniques. These techniques are capable of producing thin films. However, both

methods are more complicated and require complex setup than the three solvent based

techniques discussed in this section. These two methods are not ideal for PLF preparation

due to the complexity and cost of apparatus.

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Solvent casting, spray coating, and spin coating were selected for PLF

preparation. These are cost effective and simple to apply for PLF preparation. Also these

methods are easy to scale up. In the next section, each of PLF preparation methods are

carefully examined and discussed in detail.

2.3 PLF Preparation Experiment

Polymer Thin Films were prepared with three different methods: solvent casting,

spin coating, and spray coating. These three methods were easy to implement and provide

consistency in producing PLFs. All three methods used a stock solution prepared with

ligand, polystyrene, and tetrahydrofuran. The detailed discussion on the stock solution is

given in following section. The stock solution was only slightly modified for the spray

coating method to help the solution to easily flow through the nebulizer.

2.3.1 PLF Stock Solution

The stock solution was the starting point in preparing Polymer Ligand Film (PLF).

The stock solution is prepared by mixing three components: ligand, polymer, and solvent.

Each component has its unique role and is equally important in generating the PLF for

analyte extraction. The role of each component will be reviewed in this section.

The ligands are the only component within PLF that show any affinity to

radionuclides and provide active sites for the analytes extraction. It is important to select

ligands that have a strong affinity to the analyte of interest to maximize extraction by

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forming a strong bond. The amount of ligand present in the PLF also plays a critical role

in the extraction efficiency. Several ligands are commercially available for radionuclide

extraction.

The polymer component in PLF plays a critical role in determining the film

structure stability. The structure stability of the film is important since PLF medium is

directly exposed to various concentration of nitric acid during analyte extraction process.

PLF must withstand nitric acid exposure. The thin film also must maintain its structure

rigidity during analysis. The film medium is investigated with various analytic techniques

to characterize and examine performance of each PLF. Some of these analytic techniques

are performed in special condition. Alpha spectroscopy, for example, is operated under

high vacuum conditions and requires a rigid polymer structure to prevent sample

degradation during the analysis. Electron microscopy, which is used to examine the

surface of PLF, also operates in extremely high vacuum condition. The polymer support

also influences overall resolution obtained using radiometry systems. It is essential to

have a smooth surface to achieve optimal alpha spectral resolution. The rough surface

greatly degrades the resolution of the spectrum due to source self-attenuation.

The solvent is the component that dissolves both ligand and polymer into a

solution. Ligands normally dissolve in an organic solvent very easily, but the polymer, on

the other hand, is generally harder to dissolve. Solvents that are commonly used to

dissolve polymers are listed in Table 2-2.

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Table 2-2 Commonly used solvents to dissolve polymers Polymer Solvent Polystyrene Toluene, Benzene, Chloroform,

o-dichlorobenzene Poly(ethylene oxide) Toluene, distilled water Poly(vinyl alcohol) Distilled water Poly(vinyl chloride) N, N-dimethylacetamide (DMA), cyclohexanone,

acetone/carbon disulfide Poly(vinylidene fluoride) Tetrahydrofuran Poly(ethylen terephthalate) Tetrachloroethylene, hexan Polycarbonate Chloroform, dichloromethane Polyethylene 1,2,4-trichlorobenzene, decalin, di-namyl

ether, halogenated hydrocarbons, higher aliphatic esters and ketones, hydrocarbons, xylene (Above 80 oC for high density and 20-30 oC lower for lower density polyethylene)

Nylon 11 Trifluoroacetic acid (TFA) Polysulfone Chlorobenzene

Five different ligands were used in this study: bis(2-ethylhexyl)

methanediphosphonic acid, di(2-ethyl hexyl) phosphoric acid, trialkyl methylammonium

chloride, 4,4'(5')-di-t-butylcyclohexano 18-crown-6, and 2-ethylhexyl 2-

ethylhexylphosphonic acid. Polystyrene was exclusively used as a polymer support in this

research due to the rigidity it provides to the PLF and the good alpha spectra resolution

achieved with PLF synthesized with it. The ligands and polystyrene were dissolved with

tetrahydrofuran (THF). Physical properties of polystyrene and THF are listed in Table

2-3. THF is one of the most effective polar ethers in dissolving polystyrene bead and

ligands. THF is not commonly used for polystyrene, but it is moderately toxic compared

to other solvents. Commonly used solvents are toluene, benzene, chloroform, and o-

dichlorobenzene. The danger associated with THF is its tendency to form peroxide when

exposed to air [35]. The explosive danger can be easily mitigated by using an inhibitor

and completely sealing off the solvent from oxygen.

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The pictures of stock solution are shown in Figure 2-5. It normally takes about

two days to completely dissolve polystyrene beads and only a short time to dissolve

ligands in THF. The stock solutions were mixed with a vortex mixer before each use to

ensure even distribution of ligands and polystyrene. It is important to have a stock

solution with an even distribution of ligands and polymer to limit variability in PLFs

from the same batch solution.

Table 2-3 Polystyrene and Tetrahydrofuran properties Polystyrene Tetrahydrofuran Molecular Formula [CH2CH(C6H5)]n C4H8O Density (g/mL) 1.05 0.889 Boiling Point (ºC) N/A 65-67 Melting Point (ºC) 240 -108 Flash Point (ºC) N/A -17.2

Ligands used in this experiment were purchased from Eichrom Technologies, Inc.

The polystyrene beads and THF were obtained from Sigma-Aldrich. All chemicals were

used without further purification.

Figure 2-5 PLF stock solution (A) with un-dissolved polystyrene, (B) with polystyrene completely dissolved

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Ligand, polystyrene, and THF were weighed with an analytical balance to have

precise amount of chemicals in the stock solution. For each ligand, several stock

solutions were prepared by varying the mass of ligand to examine effect of the ligand

mass on the analyte extraction performance. The amount of polymer in solution was kept

constant at around 2.8g and the mass of ligand was varied from 0.147g to 2.8g. Each

stock solution was described as the ratio between ligand and the entire solid mass. For

example stock solution with one part ligand and one part polystyrene was assigned 1:2

(w/w) ratio. Ligand and polymer mixture was dissolved with about 14g of THF.

2.3.2 Solvent Casting Method

Solvent casting method is the simplest of the three sample preparation techniques.

Most PLFs were prepared by this method. This method is capable of generating a smooth

surface and a uniform thickness PLF with minimum intervention. In this method,

polymer ligand stock solution is directly stippled onto a 33 mm diameter stainless steel

substrate to form a PLF. Roughly about 1 to 1.5 mL of the solution is deposited on a

substrate using this method. THF is highly volatile and polymer starts to solidify in a few

hours after stock solution is stippled onto a substrate. PLFs were placed in a fume hood

overnight to evaporate THF and leaving only solidified film on the substrate. PLFs

prepared with solvent casting deposited about 220 mg of polymer after evaporation of

THF. Figure 2-6 is a 1:5 HDEHP PLF prepared with the solvent casting method.

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Figure 2-6 PLFs prepared with solvent casting method

The color of PLF generated from this technique differs based on the type of ligand

used and the amount that is mixed into the stock solution. The polystyrene used is clear in

its natural form and the ligand is the only component causing the color change. A large

amounts of ligand in a stock solution generally turns the PLF to a more opaque color

once THF is completely evaporated.

Some PLFs form bubbles along the edge of the film. These bubbles have a

tendency to develop in clear color PLFs. The bubbles are suspected to be from the THF.

It is believed that some of THF is encapsulated in the polymer medium as PLF solidifies.

These THF bubbles are generated on the entire medium and then migrate to the edge and

start combining into a larger size. As the bubble grows in size, it causes polymer film to

expand on the edge as shown in Figure 2-7.

Figure 2-7 Crown ether PLFs with large population of bubbles along the edge

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Further tests were carried out to test possibility of THF encapsulated on PLF. First, PLFs

were placed under the heat lamp to cause any THF in a polymer medium to boil. The

boiling point of THF is around 65 oC, and temperature under the heat lamp reaches up to

90 oC. Bubbles slowly formed on the PLF once temperature reached around 90 oC.

Bubbles did not migrate towards the edge as observed during PLF preparation. Most

bubbles burst and disappeared as THF escaped from the PLF medium. The second

experiment used a furnace to expedite the formation of bubbles. Temperature was set

around 150 oC and formation of bubbles was faster than when the heat lamp was used.

The bubbles generated in the furnace still only traveled vertically and no horizontal

movement was observed. Both in the heat lamp and furnace experiments, boiling of THF

caused localized expansion of polymer film and unevenness on the PLF surface. The

unevenness of the surface maybe resurfaced by raising the temperature to get polystyrene

to slightly melt and expanded area to re-level. Applicability of thermal resurfacing is

depended on ligand used in the PLF. HDEHP based PLFs work well with this operation.

However, H2DEH[MDP] based PLFs cracked once removed from furnace and cooled.

There are a few limitations in preparing PLF with this technique. First, there are

limited choices of materials that can be used as a backing plate for the film. THF is a

moderately polar solvent, which is capable of dissolving a wide range of nonpolar and

polar chemical compounds. A large amount of THF is used in preparation of PLF, and it

is enough volume to damage any backing material that is dissolvable by THF. This limits

most of the polymer substrates from being used as the backing plate. Figure 2-8 shows

damage caused by THF on nitrile and latex substrates. Also, the large volume of solution

used to generate PLF causes emission of large amount of volatile organic compounds.

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Figure 2-8 A Latex and Nitrile substrates damaged by THF

2.3.3 Nebulizer Spraying Coating Method

The nebulizer method is developed to prepare a thin PLF by spraying a solution

on a backing material. In this technique, the stock solution is slowly fed into the nebulizer

aperture using a syringe pump, and nitrogen is fed in from the bottom outlet to generate

aerosol droplets of polymer ligand solution as shown in Figure 2-9. The technique is

capable of producing extremely thin film with minimal use of stock solution. The

nebulizer spraying method expands the possibility of applying PLF on many different

shapes and materials. In this method, THF aerosols evaporate instantaneously and only

polymer and ligand reach the substrate, which eliminates the possibility of THF

damaging the substrate.

Figure 2-9 Nebulizer setup for PLF spraying

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The PLF stock solution was slightly modified to be used with the nebulizer. The

regular stock solution starts clogging the nebulizer capillary after spraying about 4 mL,

causing uneven flow. The stock solution was diluted with THF to make the solution less

viscous to prevent clogging of the capillary. About 40 g of THF was used for 2.2 g of

polystyrene.

The nebulizer used in this experiment was manufactured by Meinhard®. The

nebulizer is rated for up to 1 L/min at 50 psi. The capillary inner diameter is about 0.30

mm. The stock solution is delivered to the nebulizer by KD Scientific syringe pump at a

consistent speed of 150 µl/minute. Nitrogen was passed through the nozzle at 20 psi to

spread PLF stock solution once it left the nebulizer opening. The entire nebulizer

spraying setup is shown in Figure 2-10. The polymer ligand coating was extremely thin

and only 0.012±0.007 g of PLF was used to coat on the 33mm stainless steel substrate.

Figure 2-10 Nebulizer spray coating setup

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PLF was sprayed on several different substrates ranging from metal to polymer.

THF evaporated instantaneously as the PLF stock solution left the nebulizer nozzle and

polymer ligand mixture formed a web like structure on the substrate as shown in Figure

2-11. Once the entire surface is coated, substrate was placed in a furnace and polymer

was melted to form a film. The PLF on aluminum substrate before and after heat

treatment is shown in Figure 2-11. The polymer coating on the substrate was extremely

thin after the heat treatment. However, the coating was visibly uneven regardless of the

type of substrate used in the process. The control of the spraying apparatus was difficult

to evenly spread the polymer film onto the substrate.

Figure 2-11 Sprayed PLF (A) before heat treatment (B) after heat treatment

2.3.4 Spin Coating Method

The spin coating method is another technique that is capable of producing a thin

circular film on a flat substrate. An excess amount of a solution is placed on the substrate,

which is then rotated at high speed in order to spread the fluid by centrifugal force.

PLFs were prepared by first attaching stainless steel substrate to a spin coater.

Once substrate is securely attached, PLF stock solution is transferred to the substrate then

spun at high speed to spread solution and then remove any excess liquid from the surface.

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Spin coating conditions were varied to find optimal conditions to generate ideal thin film

for analyte extraction.

Figure 2-12 Uneven polymer film coating on stainless steel substrates by spin coating method

The PLF stock solution used in the experiment was too viscous to evenly spread

over the substrate by high speed spinning. When solution was only dispensed on the

center of the substrate only a section of the substrate was covered as shown in Figure

2-12. Also, swirl pattern can be observed in some samples, which indicates that the spin

speed was too high for the particular solution used in spin coating.

Figure 2-13 PLF spin coating setup

The optimum result was achieved by covering the entire substrate with the PLF

stock solution before spinning the substrate. Any excess liquid was removed by

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centrifugal force and only a very thin layer was coated on the substrate surface. The

substrate was spun at 750 rpm for 29 seconds. The spin coater is shown in Figure 2-13.

The white spots shown in Figure 2-13 are from the excess PLF solution that was removed

from the substrate. The technique coated 0.013±0.003 g of PLF onto the 33mm stainless

steel substrate. The total PLF mass coated on the substrate was similar to the one

generated with the spray coating method.

2.4 PLF Preparation Conclusions

Several thin film preparation methods were carefully evaluated for the PLF

synthesis. Each technique requires vastly different sample preparation apparatus and

procedures. Out of these techniques, solvent casting, spray coating, and spin coating

were selected and used to prepare PLF. These techniques were simple to implement and

required low initial setup cost. All three methods required use of THF to dissolve ligand

and polymer. Five different ligands were used: bis(2-ethylhexyl) methanediphosphonic

acid, di(2-ethyl hexyl) phosphoric acid, trialkyl methylammonium chloride, 4,4'(5')-di-t-

butylcyclohexano 18-crown-6, and 2-ethylhexyl 2-ethylhexylphosphonic acid.

Polystyrene was exclusively used as a polymer support in this research due to the rigidity

it provides to the PLF and the good alpha spectra resolution achieved with it.

Most of PLFs were prepared with the solvent casting method due to its ability to

easily scale up the production. PLFs prepared using this technique had uniform thickness

and very smooth surface. The color of PLF generated with solvent casting differs based

on the ligand and the ligand to polymer ratio. A relatively large volume of 1mL of stock

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solution was used to prepare a PLF. The large volume of THF limits choice of backing

substrate that can be used with the method. Most polymer substrates are incompatible

with THF. Also, there were several indications that THF was encapsulated in polymer

medium as PLF solidifies. THF was so volatile that it evaporated and formed a solid

polymer layer on the top and prevented complete evaporation of solvent from the

polymer structure.

The nebulizer spray coating method expands the possibility of applying PLF on

various types of surfaces. In this method, THF aerosols evaporate instantaneously and

form a web like structure on the substrate. Once the entire surface was coated, substrate

was heat treated to melt the polymer to form a film. The polymer coating on the substrate

was extremely thin after the heat treatment. However, the coating was visibly uneven.

The spin coating method was also able to generate extremely thin polymer films. An

excess amount of stock solution was removed with centrifugal force and only thin film

was left on the substrate. Both the nebulizer spray coating and spin coating methods

deposited similar mass of PLF on the stainless substrate. , which indicates a similar film

thickness.

PLFs prepared in this chapter were tested for analyte extraction in various

conditions. Plutonium was mostly used to test PLFs. Detailed information of each PLF is

discussed in following three chapters.

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3. Chapter 3

Bis(2-ethylhexyl) methanediphosphonic acid (H2DEH[MDP])

3.1 Introduction

Bis(2-ethylhexyl) methanediphosphonic acid (H2DEH[MDP]) ligand based PLFs

were studied for plutonium and uranium extraction. H2DEH[MDP] was chosen as an

extractant due to its ability to extract actinides over a wide range of acid concentrations.

PLFs were examined in a wide range of conditions for plutonium and uranium extraction.

3.2 Theory and Background

Diphosphonic acids are known for their ability to form strong complexes with

metal ions through ionized phosphonic acid groups and P=O groups [36]. Bis(2-

ethylhexyl) methanediphosphonic acid (H2DEH[MDP]), which contains the diphosphonic

group, is known to effectively retain alkaline earth metals and actinides, particularly for

tetra and hexavalent oxidation states [37], [38]. This extractant is synthesized by mixing

one equivalent of MDPA and two equivalents of 2-ethylhexanol in dry tetrahydrofuran

(THF). The mixture is refluxed and a solution of dicyclohexylcarbodimide is added

dropwise over a period of three hours. The solution is refluxed for three more days. The

crude product is obtained by evaporating the solvent under reduced pressure. Further

purification is done by dissolving the crude product in warm 1 M ammonium hydroxide

and impurities are extracted with CH2Cl2. HCl is then added to adjust pH to below 1 and

a purified compound is extracted with CH2Cl2 [39]. The chemical structure of Bis(2-

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ethylhexyl) methanediphosphonic acid (H2DEH[MDP]) is shown in Figure 3-1.

H2DEH[MDP] is a clear and extremely viscous oil that is insoluble in water, but soluble

in organic diluent [37], [38], [40]. The two phosphoryl groups in the extractant are very

effective in retaining actinides, particularly for tetra and hexavalent oxidation states [37],

[38].

Figure 3-1 Chemical structure of H2DEH[MDP]

H2DEH[MDP] exists in dimeric form in organic diluents. Dimerization is

achieved by displacement of H+ ion from the H2DEH[MDP] molecule and through strong

hydrogen bond interaction between the phosphoryl and P-OH groups [41].

Studies have shown that selectivity of H2DEH[MDP] among the alkaline earth

metal ions is independent of acidity [39], [41]. Alkaline earth metals are extracted from a

solution by two dimeric H2DEH[MDP] molecules. The alkaline metal is captured by a

number of six-membered chelate rings through metal and P=O bonds in the center of a

complex molecule as shown in Figure 3-2 [39].

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Figure 3-2 Alkaline earth metal extraction mechanism with H2DEH[MDP]

Am(III) is also extracted in a similar manner with the metal ion bonded to two

dimeric extractants and with three H+ ions displaced to neutralize the charge on the metal

ion [41]. The exact extraction chemistry for Fe(III), U(VI), and Th(IV) has not been

reported. It is only expected to be more complicated than alkaline earth metals and

Am(III).

H2DEH[MDP] is used by Eichrom Technologies, Inc. to manufacture their

Acinide® resin. The resin is produced by coating H2DEH[MDP] onto 20-50 um size

Amberchrom CG-71ms acrylic ester resin beads [37]. The main application for this

particular resin is for group actinide separations and gross alpha measurements. The

manufacturer’s data on this resin shows extremely high k’ for Am(III), Pu(IV), Th(IV),

Np(IV), and U(VI) as shown in Figure 3-3 [42]. The high k’ is an indication that

extractant has high affinity for that particular analyte.

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Figure 3-3 H2DEH[MDP] distribution ratio dependency on HCl concentration for various ions

3.3 Plutonium and Uranium Extraction

H2DEH[MDP] based PLFs were tested for plutonium extraction in various

conditions. Several different ratio PLFs were first tested over various nitric acid

concentrations. The amount of ligand plays a critical role in extraction capability and

integrity of PLF. Also, the extraction of analytes using ligands showed high dependency

on the pH in liquid/liquid extraction. Since the ligands are incorporated into a polymer

support matrix, the extraction dependency on solution pH may differ from liquid/liquid

extraction cases. It is important to find the optimal amount of ligand that will provide the

best analyte extraction and at the same time provide a robust film structure.

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3.3.1 Analyte Extraction Characterization

1:5, 1:10, and 1:20 ratio H2DEH[MDP] PLFs were tested over 0.01 to 8M nitric

acid solutions to generate baseline plutonium extraction performance. 1:2 PLF was also

prepared for the study, but it was not structurally robust to use with the nitric acid. 239Pu

solutions used in this study were prepared with 0.01, 0.1, 1, or 8M nitric acid solution.

Plutonium tracer solution was first dried on a hot plate then re-dissolved in a

concentration adjusted nitric acid solution. For the PLF testing, 2.5 to 3mL 239Pu tracer

was directly stippled on the PLF surface, allowing the analyte to equilibrate for 3 hours

before removing the solution. Solution volume was selected to cover the entire PLF

surface. Some of the tracer solution evaporated during the equilibration time but left

anywhere from 1 to 2 ml solution on the PLF substrate. Tracer solution left on the PLF

was collected and electrodeposited to measure plutonium activity left in the solution.

After removing the tracer solution, PLFs were thoroughly rinsed with deionized water to

remove any nitric acid remaining on the surface and to remove any tracer that was not

bound to the surface. PLFs were then allowed to air dry to remove any water that may

have been left on the polymer medium. The plutonium activity of each sample was

measured by direct alpha counting to quantify the plutonium recovery by H2DEH[MDP]

PLF.

Octet Plus system from Ortec, equipped with 900 mm2 ion implanted silicon

detectors, was used in the entire experiment performed in this study. The vacuum

chambers can accept sample size up to 51mm and chambers were large enough to accept

all PLF samples. However, the sample tray provided with the detector system was not

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designed for the PLF analysis. PLFs could not be secured to the tray and it had a

tendency to move out of position when vacuum was applied. This might cause inaccurate

activity measurement as the sample would move out of the detector line of sight. Also,

the consistency of the PLF placement relative to the detector could not be ensured in this

setup. This caused inconsistent activity measurement from sample to sample. The sample

trays were modified by cutting a hole in the middle to have the PLF substrate sit securely

on the tray. This modification eliminated sample movement during the analysis and

increased the consistency in sample analysis condition. The modification ensured

consistent sample placement in the vacuum chamber and also provided easier sample

handling. The picture of the sample tray before and after the modification is shown in

Figure 3-4.

Figure 3-4 Alpha spectroscopy sample tray (A) before modification (B) after modification

The plutonium recovery by H2DEH[MDP] PLF showed a dependence both on the

nitric acid concentration and the composition of the polymer film. H2DEH[MDP] PLF

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was able to extract plutonium in all nitric acid concentration tested as shown in Figure

3-5. Both 1:10 and 1:20 PLFs were effective for plutonium extraction from 0.01 to 1M

nitric acid. There was no statistical difference in plutonium recovery between 1:10 and

1:20 PLF at each nitric acid concentration from 0.01 to 1M. The highest recovery for

both PLFs occurred at 1M tracer solution. The percent recoveries were 50.44±8.27 and

47.61±7.17 for 1:10 and 1:20 PLF, respectively. The plutonium recovery for 1:5 PLF was

noticeably lower than the other two from 0.01 to 1M. However, the recovery was higher

at 8M than other two PLF types tested.

Figure 3-5 The baseline performance of H2DEH[MDP] PLF in plutonium extraction as a function of nitric acid concentration

The plutonium extraction study was further expanded to include other PLF compositions

to have more detailed picture on the role of the composition in the extraction efficiency.

1:15 and 1:25 PLFs were prepared and tested in same manner as other H2DEH[MDP]

PLFs. 1:15 PLF followed the plutonium extraction trend shown by 1:10 and 1:20 PLFs.

Figure 3-6 shows a similarity of 1:10, 1:15, and 1:20 PLFs in plutonium extraction. 1:25

0

10

20

30

40

50

60

70

0.01 0.1 1 10

Pu re

cove

ry (%

)

Nitric concentration [M]

1:5

1:10

1:20

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PLF was unstable and showed tendency to develop large bubbles while in the vacuum

chamber of the alpha spectroscopy system. 1:25 PLF with large bubbles is shown in

Figure 3-7. About 90% of 1:25 PLFs developed bubbles and in some cases polymer film

shattered into pieces. The bubbles were believed to be caused by gas trapped in the

polymer structure, most likely THF. Larger ligand content in PLF is believed to provide

more porous surface for gas to escape from the polymer structure. In 1:25 PLF, which

contain lowest amount of ligand, large amount of gas is being trapped during PLF

synthesis due to inadequate venting. Once vacuum was applied trapped gas in PLF

ballooned the surface as it escapes from polymer structure. Due to the stability issue, 1:25

data was not included in Figure 3-6.

Figure 3-6 Plutonium recovery by 1:10 through 1:20 H2DEH[MDP] PLF as a function of nitric acid concentration

0

10

20

30

40

50

60

70

0.01 0.1 1 10

Pu re

cove

ry (%

)

Nitric concentration [M]

1:10

1:15

1:20

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Figure 3-7 1:25 H2DEH[MDP] PLF with damaged surface

It was expected for 1:5 H2DEH[MDP] PLF to have the highest recovery due to

higher number of ligands presented in the PLF compared to 1:10, 1:15, and 1:20 PLFs.

Ligand is the only component within the PLF to have any significant affinity to

plutonium and the more ligands means more binding sites for plutonium. This result

clearly shows that the plutonium extraction is not only dependent on the amount of ligand

presented in the PLF but many other factors, such as ligand orientation, ligand

complexation, and plutonium oxidation state. Plutonium has five oxidation states, and up

to four different oxidation states can co-exist in a solution [43]. It was impossible to

measure the plutonium oxidation states in the solutions used in the experiment due to low

plutonium quantity in each solution. However, it is suspected that both +3 and +4

oxidation states co-exist in the tracer solution [43]. The H2DEH[MDP] have shown

effectiveness in both Pu(III) and Pu(IV). The H2DEH[MDP] ligands are theorized to

form various length complexes with each other as the PLF is synthesized and plutonium

extraction behavior changes based on the length of the complex. This means that certain

complexes are only effective for Pu(III) extraction, and the other complexes are only

effective for Pu(IV). More ligands in the stock solution seems to cause H2DEH[MDP] to

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form complexes that are mostly effective for Pu(IV) extraction. As the amount of ligand

in the stock solution decreases, two distinctive ligand complexes form, one for Pu(III)

and the other for Pu(IV). Another possible explanation for the plutonium extraction

behavior observed is that nitric acid is changing the orientation of ligands to be more

favorable for plutonium extraction at certain nitric acid concentrations. For example,

ligands in 1:10, 1:15, and 1:20 PLFs are oriented more favorably for plutonium extraction

at 0.1 or 1M nitric acid.

Tracer solutions left on the PLFs were collected after 3 hour exposure to measure

plutonium activities that were not extracted by PLFs. Each sample was traced with 242Pu

and electrodeposited for the analysis. Samples were prepared on 5/8 inch stainless steel

substrates using sulfuric acid based electrolytes. The addition of plutonium recovered

from the PLF and the electrodeposited sample was expected to be close to 100%;

however, in most samples, the recovery was below 100%.

Figure 3-8 Unaccounted plutonium by H2DEH[MDP] PLF as function of nitric acid concentration

0

10

20

30

40

50

60

70

0.01 0.1 1 10

Pu re

cove

ry (%

)

Nitric concentration [M]

1:5

1:10

1:20

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Unaccounted plutonium activities are plotted and shown in Figure 3-8. About 20 to 40%

of the activities were unaccounted for PLFs tested with 0.01 to 1M nitric acid. There was

no missing activity dependency based on the PLF compositions from 0.01 to 1M nitric

acid. PLFs tested with 8M nitric acid, however, showed considerably different behavior

than ones tested with 0.01 to 1M. With 8M nitric acid, unaccounted 239Pu activity

increased as a function of ligand mass in PLF. Figure 3-9 was prepared with only 8M

nitric acid data to better show the changes in missing activities by different composition

PLFs.

Figure 3-9 Unaccounted plutonium activity with 8M nitric acid

It is inevitable that some activity will be lost during the sample preparation

process due to multiple solution transfer involved in the procedure. However, the missing

activities are too great to be only associated to the activities lost during the sample

preparation. The missing plutonium activities observed for samples are most likely

caused by analyte depositing below the surface of a PLF. Plutonium deposited below the

surface will not be measured by alpha spectroscopy due to the heavy charged particle

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interactions causing energy from alpha particles to be absorbed by PLF. The total activity

deposited on the H2DEH[MDP] PLF will most likely be higher than the one measured

with alpha spectroscopy.

There are two possibilities on how the plutonium is deposited below the surface.

The first possibility is tracer solution penetrating through the space between the stainless

steel substrate and the PLF body. The second possibility is that PLF is permeable to the

nitric acid solution and plutonium is depositing on the entire polymer body. It is

important to know the penetration mechanism to control or manage the overall analysis.

Figure 3-10 Plutonium penetration mechanism experiment by varying tracer solution volumes

The penetration mechanism was studied by varying plutonium tracer volume

stippled onto the PLF to adjust area covered by the tracer solution. Three different

volumes, 1, 2, and 3 mL, were used in the study. Figure 3-10 shows how much surface

the tracer solution covered at different solution volumes. 1 mL of tracer solution covered

only a portion of the PLF surface, and it stayed away from the edge of the PLF. 2 mL

solution also only covered a portion of the surface, but some of solution touched the edge.

The largest volume used, 3mL, was able to cover the entire surface. Each sample was

prepared in an identical condition except for the tracer volume. Any tracer left on the PLF

surface was collected after exposure. The collected tracer solution was electrodeposited

onto a 5/8 inch stainless steel for alpha spectroscopy. Plutonium activity deposited on the

surface and activity left on the tracer solution were listed in Table 3-1. Assuming that

most missing activity was deposited on the PLF medium, it is shown that the normalized

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penetration activity has no dependence on the tracer solution volume. This result

indicates that analyte was penetrating through the entire PLF surface, and there was no

gap between the stainless steel substrate and the PLF to allow analyte penetration.

Table 3-1 Plutonium penetration dependency on solution volume Solution Volume

(mL) PLF Recovery (%) Electrodeposition

Recovery (%) Unaccounted Activity (%)

1 28.19±4.75 19.15±2.92 52.66±3.53 2 28.87±4.20 19.90±2.23 51.23±1.97 3 29.21±8.63 14.49±3.19 56.30±5.55

This phenomenon of analyte depositing through the depth of the PLF gives one

major advantage in destructive analysis, such as mass spectroscopy. The PLF technique is

developed as a screening method and the goal is to perform destructive analysis on

selective samples to gain much needed isotopic information in the shortest possible time.

Larger amounts of analyte present in the PLF gives better chance of performing precise

analysis to gain analyte isotopic information. Figure 3-11 is a schematic view of

radionuclides extraction by PLF, where analytes are depositing on surface and throughout

the depth of the film.

Figure 3-11 Schematic diagram of PLF analyte extraction mechanism

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One of the possible issues arising from analyte penetrating phenomenon is the

potential for degradation of alpha spectrum. The alpha spectrum resolution is extremely

dependent on the quality of the source. In most cases, the best resolution is achieved with

clean, thin, and uniform layer samples. Multi-layer samples tend to have a broad

spectrum peak due to a source self-attenuation. The spectrum resolution from the PLF

was compared to the resolutions attained with electrodeposited samples to measure the

effect of analyte penetration on the spectral resolution. The spectra were analyzed by

fitting the peaks with Bortels’ equation, which is given in Equation 3.1.

𝑓(𝑥) = �ℎ𝑖𝜎√2𝜋

2𝜏𝑒𝑥𝑝 �

𝑥 − 𝜇𝑖𝜏

+𝜎2

2𝜏2� 𝑒𝑟𝑓𝑐 �

1√2

�𝑥 − 𝜇𝑖𝜎

+𝜎𝜏��

𝑛

𝑖=1

Equation 3.1

where n is number of peaks, μ is the mean, σ is the standard deviation, τ is the distortion,

and h is the height of a peak. The resolution of the detector systems was determined by

measuring a full width at half maximum (FWHM) of the peak. The FWHM was

calculated from the Gaussian width or standard deviation of the peak using Equation 3.2.

The FWHM and distortion term, τ, were used to compare peak broadening.

𝐹𝑊𝐻𝑀 = 2√2𝑙𝑛2𝜎 ≈ 2.35𝜎 Equation 3.2

All four H2DEH[MDP] PLF compositions showed similar FWHM and distortion in the

nitric acid range tested as shown in Table 3-2. Variations in peak fitting terms between

samples were low, which indicate consistent peak shape between samples. The resolution

and distortion were comparable to the one achieved with a typical electrodeposition

sample.

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Table 3-2 Average FWHM and Tailing for H2DEH[MDP] PLFs tested for plutonium extraction PLF ratio Nitric Acid (M) FWHM (keV) Tailing 1:5 0.01 19.42±1.08 23.70±2.18 1:5 0.1 18.81±1.39 24.63±0.69 1:5 1 19.35±2.94 28.20±2.40 1:5 8 12.74±1.62 24.72±1.02 1:10 0.01 19.86±1.50 20.49±1.76 1:10 0.1 18.44±0.83 21.48±0.34 1:10 1 18.81±2.01 21.48±0.98 1:10 8 20.71±2.49 24.49±4.46 1:15 0.01 24.71±3.83 19.35±2.83 1:15 0.1 25.94±1.44 21.03±1.20 1:15 1 26.51±1.54 20.11±0.88 1:15 8 23.83±6.60 17.90±1.17 1:20 0.01 19.99±2.70 19.90±2.49 1:20 0.1 21.15±1.65 19.22±1.01 1:20 1 17.89±2.18 19.83±0.72 1:20 8 18.42±3.68 14.52±3.34

1:10, 1:15, and 1:20 PLFs were all suitable for plutonium extraction. Out of three

compositions, 1:20 used the least amount of H2DEH[MDP] ligands to manufacture PLFs,

which makes it more cost effective. Due to the cost saving, 1:20 PLF was more closely

inspected for plutonium extraction.

3.3.2 Time Dependency Test

The equilibration time of 3 hours was used in the previous section to generate a

baseline for plutonium extraction behavior for the H2DEH[MDP] PLF. The time was

chosen to provide enough time for ligands to form complexes with the plutonium.

However, the PLF method is being developed to rapidly process samples and shorter

equilibration time is always preferred. It is important to examine plutonium extraction

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dependency on equilibration time to decrease analysis time. In this experiment, 1:20

H2DEH[MDP] PLF was tested with 0.1M nitric acid.

The extraction condition was kept consistent throughout the experiment except for

the exposure time. The exposure times used in this experiment were from 10 to 180

minutes. The plutonium recovery linearly increased from 10 to 90 minute exposure time

then started to level off after 90 minute exposure time as shown in Figure 3-12. The

maximum plutonium recovery of 44% was achieved at 180 minute equilibration time.

However, the standard deviation at 180 minute exposure time was larger than other

measurements. 90 min and 120 min recoveries were within the standard deviation of the

180 min recovery. Student’s t-test was performed to confirm and assess the statistic

difference between plutonium recoveries between 90 to 180 minutes. The recoveries

measured at 90 and 120 min exposure time was statistically indifferent from the 180 min

measurement at 95% confidence level.

Figure 3-12 H2DEH[MDP] PLF plutonium recovery at different exposure time

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The most important aspect that can be gathered from this time study is that the

PLF was able to extract plutonium even at 10 min equilibration time. The recovery was

only slightly higher than 10%, however, even 10% may provide sufficient activity to

perform a radiometric analysis depending on the sample activity. In a post-detonation

situation, sample activity near ground zero will be high enough for even a very short

equilibration time to extract enough plutonium for a radiometric analysis. In the case of

an environmental sample, which will typically have low activity, 10% recovery most

likely will not provide enough analyte for reliable radiometric analysis. However, if the

PLF technique is only used as a screening method before performing a more precise

analysis, this technique can be utilized to decrease total sample numbers and shorten the

total analysis time. Alpha spectroscopy can be used to measure any plutonium activity

above background level and plutonium can then be back-extracted from a PLF for mass

spectroscopy. The mass spectroscopy analysis only requires a trace amount of plutonium

to reliably perform an isotopic measurement. In the case of Thermal Ionization Mass

Spectroscopy (TIMS), approximately 100 femtogram of plutonium is needed for analysis

with a routine sample preparation method. The detection limit can be even lower with

more sophisticated sample preparation methods, such as resin bead loading, carbonized

filament, and etc. 100 femtogram of 239Pu translates to about 1.399x10-2 dpm, and other

plutonium isotope activities are listed in Table 3-3. Silicon alpha detectors are not

sensitive to measuring any decay energy given from plutonium isotopes listed in Table

3-3. TIMS analysis can be reliably performed if any activity is measured from the sample

using alpha spectroscopy.

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Table 3-3 Plutonium activities per 100 fg of analyte Plutonium Isotope Alpha Activity for 100 fg analyte(dpm) 239Pu 1.399x10-2 240Pu 5.106x10-2 242Pu 8.880x10-4

3.3.3 Consistency Study

It is enormously important to have consistency in analyte recovery for PLFs to be

used as a reliable sample preparation method. The recovery does not necessary have to be

high but it must be consistent and reproducible. There are two main possible causes for

the inconsistent PLF plutonium extraction efficiency. The first source of the inconsistent

analyte extraction is due to variability in PLF itself. The second possible cause of the

inconsistency is the plutonium oxidation state discrepancy between tracer solutions. The

plutonium oxidation effect on extraction efficiency was already discussed in 3.3.1

Analyte Extraction Characterization section in this chapter. There may also be a small

inconsistency in activity measurement resulting from a counting uncertainty. However,

measurement variation due to the counter system should be minimal compared to PLF

variation or plutonium oxidation variation.

The data from the previous experiments showed a large standard deviation from

1:20 PLFs that were tested with 0.1M tracer solution for 3 hour equilibration time. This

high variation could have been a result of either PLF variation or oxidation state

difference in solutions used. The PLFs used in previous experiments were prepared and

used as needed and so were the 239Pu tracer solutions. In other words, no controlled

experiment was carried out to carefully test the PLF consistency. The plutonium

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oxidation states are hard to control in a real world situation and the focus was on

examining the consistency of the PLF itself.

The experiment was designed to test the PLF consistency with 1:20

H2DEH[MDP] PLF and 0.1M nitric plutonium tracer solution. For this experiment, two

1:20 H2DEH[MDP] PLF stock solutions were prepared on a different date. The stock

solutions were carefully prepared to minimize inconsistency. The amounts of each PLF

component used in the stock solutions are listed in Table 3-4. These two stock solutions

were used to synthesize two batches of PLFs. There was no visible difference between

two batches of PLFs as shown in Figure 3-13.

Table 3-4 Mass of components used to prepare two H2DEH[MDP] PLF batches for the consistency study Batch 1 Batch 2 H2DEH[MDP] (g) 0.291 0.298 Polystyrene (g) 5.672 5.586 THF (g) 28.105 28.013

Six PLFs from each batch were selected for the experiment; a total of 12 samples were

prepared by stippling 3 ml of 0.1M 239Pu tracer solution on each PLF. The standard

equilibration time of three hours was used in the experiment. Each sample was counted in

six different detectors to measure 239Pu activity deposited on the PLF. Samples were

counted in multiple detectors to measure activity variability caused by the detector

system.

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Figure 3-13 H2DEH[MDP] PLFs from two batches

The plutonium recoveries by PLFs are plotted in Figure 3-14. There were slight

differences in activities measured as samples were counted by six different 900 mm2

alpha detectors. However, as shown in Figure 3-14, the trends were similar for all

detectors; the plutonium recovery for sample 5 was considerably lower than other

samples. Sample 5 was deemed an outlier, and it was excluded from the data analysis.

Figure 3-14 Plutonium recoveries by two different batch 1:20 H2DEH[MDP] PLFs with 0.1M nitric acid solution

15.00

20.00

25.00

30.00

35.00

40.00

45.00

0 1 2 3 4 5 6 7 8 9 10 11 12 13

Plut

oniu

m R

ecov

ery

(%)

Sample #

Detector1

Detector2

Detector3

Detector4

Detector5

Detector6First set Second set

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The variability between the batches was examined by computing the plutonium

percent recovery mean from six PLFs from each batch as shown in Table 3-4. The second

batch consistently showed higher recovery than the first batch, but the values were within

the standard deviation. Based on this data, the plutonium recovery was not significantly

different from the first batch to the second batch. The overall plutonium recovery showed

about 16 to 17.5% standard deviations in this experiment depending on the detector.

Table 3-5 Average plutonium recovery by each batch First Batch Second Batch Overall

Detector 1 33.12±3.30% 36.34±4.12% 35.23±3.25% Detector 2 33.19±3.23% 35.43±3.57% 34.76±3.64% Detector 3 35.16±3.03% 38.51±3.54% 37.36±3.75% Detector 4 32.48±3.64% 37.56±3.73% 35.61±4.52% Detector 5 32.09±2.33% 36.75±3.85% 34.98±4.03% Detector 6 32.87±3.56% 36.53±3.38% 35.22±3.95%

The PLF method was developed to be used as an alpha source preparation

method. It is important to compare PLF standard deviation to the standard deviation

normally observed in an electrodeposition sample preparation, since the electrodeposition

method is the most widely used alpha source preparation technique. Ten electrodeposited

239Pu samples were carefully prepared and samples were counted under the 450mm2

alpha particle detectors. The electrodeposited samples had about 17.6% standard

deviation, which was very similar to one observed from the PLF method.

The total surface plutonium recoveries by H2DEH[MDP] PLF were consistently

lower than one observed with combination of column separation and electrodeposition.

However, H2DEH[MDP] PLF is capable in providing consistent plutonium recovery that

are similar to the consistency seen in electrodeposition samples.

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3.3.4 Blind Study

All of the previous sections looked into characterizing PLF behavior in plutonium

extractions. Only known activity samples were processed and analyzed with alpha

spectroscopy. An experiment was designed to verify ability of H2DEH[MDP] PLF to

process unknown samples and pin point the activities of the samples. Six unknown 239Pu

samples were prepared by a third person with no activity indication on beakers. Each

sample was traced with 242Pu then dried on a hotplate. Once samples were all dried, those

were brought back up with 3mL of 1M nitric acid. Each sample was directly stippled on

to 1:20 H2DEH[MDP] PLF and equilibrated for 3 hours. These samples were directly

counted with alpha spectroscopy for 24 and 96 hours. Once data was processed, the

measured activity of each sample was compared with the actual activity.

Table 3-6 Plutonium activity measurements from blind samples using 1:20 H2DEH[MDP] PLF

Known Activity (dpm) 24 hour counting (dpm)

96 hour counting (dpm)

Sample 1 17.86±1.12 19.03±0.47 17.49±0.33 Sample 2 8.88±0.57 7.65±0.32 8.56±0.21 Sample 3 8.83±0.56 8.23±0.28 9.05±0.20 Sample 4 0.00 0.02±0.03 0.01±0.01 Sample 5 3.30±0.23 4.37±0.19 4.27±0.12 Sample 6 1.72±0.15 1.62±0.14 1.78±0.08

The 96 hour counting time gave more accurate measurement as expected. Every

measurement was within the uncertainty of the true activity except for sample 5 as shown

in Table 3-6. In the 24 hour count, activity measurements from sample 2 and 5 were

slightly outside of the true activities. The activity measurements from sample 5 were

consistently higher than the true value in both 24 and 96 hour counting. Sample 5 was

counted in different detectors to eliminate possible systematic error caused by the

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counting system. The detector system itself was not the cause of the deviation in

measurement. The inaccurate measurement could have been a result of inconsistent

delivery of 242Pu tracer solution. The tracer solution was volumetrically measured and

delivered using micro-pipette. There is a higher degree of uncertainty involved with

volumetric measurement compared to the gravimetric measurement. There is also a small

possibility of unknowingly delivering inaccurate volume with a pipette.

The blind test proves that the PLF system can be effectively used to process

unknown samples. It is important to point out that tracer recovery was significantly lower

than the electrodeposition method. For six samples processed with PLF in this

experiment, 20-28% tracer recoveries were observed. The tracer recoveries with

electrodeposition are normally around 80 to 90%. Even with this inherent limitation, PLF

system was able to pin point the activities of samples ranging from 0 to 18 dpm.

3.3.5 Alternate PLFs

Three PLF preparation methods were used to synthesis PLF samples. These

preparation methods are described in Chapter 2. Most of the experiments were carried out

with PLFs prepared by the solvent casting method. Data gathered from the solvent cast

PLF was used as a starting point in studying spray coated PLF and spin coated PLF for

plutonium extraction. Two main aspects were examined in this section: effectiveness of

alternate PLFs in plutonium extraction and effects of alternate PLFs on the alpha spectra

resolution.

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The spray coated 1:10 H2DEH[MDP] PLFs were used to test for plutonium

extraction with 239Pu tracer solutions prepared with 0.1M nitric acid. In spray coating,

only about 12 mg of polymer film is being deposited on a stainless substrate compared to

about 220 mg for solvent casting method. The amount of ligands on the surface of the

film is similar in both spray coating and solvent casting. However, overall quantity of

ligands in the film is obviously lower for spray coated PLF than one prepared by solvent

casting. The plutonium recovery with spray coated PLF was lower compare to solvent

casting PLFs. Only 1.81% of 239Pu was extracted from 0.1M nitric acid.

One possible application of spray coating method is to prepare PLF on alternate

substrates and/or non-standard shape substrates. One of the examples is preparing a PLF

on an 8 x 10 inch aluminum foil. The increase in total surface area provides larger and

more active sites for analyte extraction on the surface. This provides a better PLF design

to be used for analyte extraction from a large volume. One limitation of the large

substrate is that PLF becomes too big to place in an alpha spectroscopy vacuum chamber,

which eliminates any possibility of direct sample analysis. However, destructive analysis

still can be performed to quantify plutonium extracted with such setup.

The PLFs prepared using the spin coating method have similar masses as the

PLFs prepared with the spray coating method. The surface was noticeably smoother than

the one prepared with the spray coating. 1:20 PLFs were tested for plutonium extraction

with the tracer solutions prepared with 0.1M nitric acid. About 30.61% of 239Pu was

recovered by the spin coated PLFs. Tracer solution left on PLFs were collected and

electrodeposited to measure any plutonium that may have penetrated through the PLF.

About 53.80% of activity was unaccounted for, which was highly likely to have been

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deposited below the surface. The surface activity for spin coated PLF was about 13%

lower than one seen with the solvent casted.

3.4 Digital Autoradiography

Digital autoradiography is a great tool to study distribution of radioactive particles

on a sample. This technique works the same way as a conventional radiography except

that the process is digitized for convenience. The digitization of the entire process

eliminates a need for a darkroom and a need for developing a film using chemicals. This

saves time from exposure to analysis.

Samples were placed on an imaging plate (Fujifilm BAS-TR 2025) and kept in a

lead shielded cave for 24 to 48 hours depending on the sample activity. This particular

imaging plate is about ten to one hundred times more sensitive than film, which decreases

exposure time considerably compared to the conventional film [44]. Once the imaging

plate was removed from the sample, it was then digitally scanned using GE Typhoon

FLA 7000 system. The radiography image in Figure 3-15 was generated after 24 hour

exposure and the locations of plutonium were clearly visible over the background. The

image generated with the digital autoradiography was mathematically analyzed using

computer programs to more closely study the plutonium distribution.

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Figure 3-15 Digital autoradiography image from 1:20 H2DEH[MDP] PLF

The image was first imported into ImageJTM software to analyze plutonium

locations. The location of every particle in the image was recorded in a Cartesian

coordinate system. The particle distribution was studied by importing the coordinates

from ImageJ to the in-house developed particle distribution analysis software. The source

code is attached in Appendix A. The code was developed in C++ language in Microsoft

Windows® environment. The software divides the image into rectangular bins and counts

particles in each bin. The bin size was adjusted to give an average of 40-50 counts per bin

to achieve about 15% uncertainty in each bin. The plutonium distribution maps were

created from the processed data. Eight samples shown in Figure 3-15 were all processed,

and it all showed uneven plutonium distribution with hot spots as shown in Figure 3-16

and Appendix B.

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Figure 3-16 Plutonium distribution maps of H2DEH[MDP] PLF generated from digital autoradiography image

The location of hot spots were different from sample to sample. PLF samples were

prepared in the same condition, and percent plutonium recovery showed little difference

between samples. It is strongly suspected that local hot spots were originated from the

PLF itself. These hot spots may be the result of high localized concentration of ligands or

surface defects. Plutonium may preferentially deposit around a defect due to a surface

area increase. Also, the ligands in a defect area may be oriented in such a way that it is

more favorable for plutonium extraction.

3.5 Uranium Analysis

H2DEH[MDP] was designed for an actinide group separation and also showed

high affinity for uranium. Since uranium alpha spectra peaks are well separated from

plutonium peaks, it is possible to co-extract plutonium and uranium onto PLF then

perform alpha spectroscopy to qualify. PLFs were examined for uranium extraction using

a natural uranium tracer. Uranium stock tracer information is given in Table 3-7.

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Table 3-7 Uranium tracer activity information Uranium Isotope Activity (Bq/g)

238U 5.694±0.108 235U (2.620±0.050)x10-1 234U 5.580±0.106

The condition tested for uranium extraction was the same as the baseline

plutonium experiment; 1:5, 1:10, and 1:20 H2DEH[MDP] PLFs were tested over 0.01 to

8M nitric acid solutions. The uranium extraction behavior was entirely different than the

plutonium extraction. Neither 1:10 nor 1:20 PLF was effective in uranium extraction over

all nitric acid ranges tested. 1:5 PLF showed the highest recovery of ~30% with 1M nitric

acid as shown in Figure 3-17. Also, about 22.5% of uranium was extracted using 1:5 PLF

at 0.1M nitric acid. Data shows that H2DEH[MDP] PLF can be used to selectively extract

plutonium over uranium or simultaneously extract uranium and plutonium by changing

the composition of the PLF. For example, with 1:5 PLF, uranium can be co-extracted

along with plutonium at 0.1 or 1M nitric acid. At the same nitric acid concentration, 1:20

PLF can be used to extract plutonium over uranium.

Figure 3-17 Uranium recovery by H2DEH[MDP] PLF as function of nitric acid concentration

0

5

10

15

20

25

30

35

0.01 0.1 1 10

U re

cove

ry (%

)

Nitric concentration [M]

1:5

1:10

1:20

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The analyte selectivity based on PLF composition was further verified in the co-

extraction experiment by using mixed uranium and plutonium tracer solution. The mixed

tracer solution was prepared by drying 239Pu and natural uranium then re-dissolved in 1M

nitric acid. The standard PLF testing procedure was used with the mixed tracer solution.

4.95 dpm of plutonium and 5.24 dpm of uranium were used to prepare each sample.

The experiment confirmed that H2DEH[MDP] PLF is capable of co-extracting or

selectively extract plutonium over uranium depending on the PLF composition.

Plutonium and uranium percent recovery by each PLF is shown in Figure 3-18. With 1:5

PLF, about 23% of plutonium and 20% uranium were simultaneously extracted. Opposite

to 1:5, both 1:10 and 1:20 PLFs were preferably extracting plutonium over uranium.

Figure 3-18 H2DEH[MDP] PLF Pu and U extraction efficiency with 1M nitric acid

3.6 Mass Spectroscopy Analysis

The plutonium isotopic ratio provides critical information on the origin and

intended use of the material. Alpha spectroscopy can offer some degree of isotopic

0

10

20

30

40

50

60

1:5 1:10 1:20

Reco

very

(%)

Dipex PLF ratio

Pu

U

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information; however, it has limitations due to its resolution. For instance, 240/239Pu

measurement is impossible to make with alpha spec due to the closeness of its peaks.

This limitation is why plutonium isotopic measurements are made using mass

spectroscopy, mainly with Thermal Ionization Mass Spectrometry (TIMS). The final goal

of this project is to develop a screening method to rapidly process samples for

radiometric analysis then further perform destructive analysis on selective samples to

gain more precise measurement. This involves first back-extracting analyte of interest

from the PLF and process samples for the TIMS analysis.

Several experiments were performed to back-extract plutonium from

H2DEH[MDP] PLF substrates and perform TIMS analysis. For PLF samples, it is

essential to effectively back-extract plutonium from PLF to perform TIMS analysis.

Several different reagents were used to back-extract plutonium, including nitric acid,

deionized water, and isopropanol.

Once plutonium was back-extracted from the PLF, GV Instruments IsoProbe-T™

Multi-Collector Thermal Ionization Mass Spectroscopy (TIMS) was used for the

analysis. The system is equipped with a multiple-Faraday/ion-counting collector

assembly for precise isotopic measurement. Generally about 200 femtogram of sample is

needed to measure the plutonium isotopic ratio with techniques that was used in this

research.

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3.6.1 Back-extraction with Nitric Acid and Deionized Water

The uptake of plutonium by H2DEH[MDP] has some dependency on acid

concentration. Based on Horwitz et al., the plutonium uptake decreases as concentration

of hydrochloride increases from 0.2 to 10 M[8]. For this study, nitric acid was used

instead of hydrochloride to prevent stainless steel substrates from corroding. Also,

deionized water was used to see how dramatic change acidity affects the extraction of

analytes from H2DEH[MDP] PLF.

First, the dependency of plutonium back-extraction on the nitric concentration

was studied by placing PLFs in 3M, 8M, or concentrated nitric acid baths for about 24

hours. Extraction solution was then electrodeposited on a stainless steel substrate for

alpha spectroscopy to quantify the amount of plutonium extracted using nitric acid. The

239Pu back-extraction was ineffective with 3M and 8M nitric acid. The average plutonium

extractions were 9.87±4.18% and 3.93±4.00% for 8M and 3M nitric acid, respectively.

The 239Pu recovery was the highest with concentrated nitric acid. The percent recovery

was over 100% as shown in Table 3-8. The possibility of introducing impurities or

contamination during the sample preparation process was ruled out due to consistent high

recovery in the entire sample population. Also tracers and reagents used in the process

were inspected with mass spectroscopy for presence of plutonium and no significant

239Pu was measured.

The percent recoveries were calculated based on the alpha spectroscopy

measurement. This means that only the PLF surface activity was used to calculate a back-

extraction recovery. A higher than 100% analyte recovery confirms that unaccounted

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activity discussed in 3.3.1 Analyte Extraction Characterization section is indeed being

deposited on the entire body of the PLF not just on the surface. Based on an assumption

that all unaccounted activity is being deposited on the PLF, percent back-extraction was

adjusted to reflex the unaccounted activity. The adjusted percent recovery for

concentrated nitric acid was well below 100% and percent recoveries for the rest of

reagents are shown in Table 3-8.

Table 3-8 Plutonium back-extraction with nitric acid and DI water

The same experiments were performed with deionized (DI) water to back-extract

plutonium from the PLF. The ligand is normally used in acidic condition and placing it

under DI water has potential to change the characteristic of the ligand. Ultrapure

deionized water used in the experiment was obtained from Barnstead Fi-Stream II Glass

Still purification system. About 50% of the plutonium was removed based on surface

activity measurement, and 19% was extracted based on the entire PLF activity.

Plutonium back-extraction was effective with concentrated nitric acid and DI

water. The activities back-extracted in these experiments were high enough to perform

TIMS. However, a considerable amount of activity was still left on the PLF based on the

unaccounted activity data. It is always advantageous to fully back-extract analyte of

interest from PLF to perform destructive analysis. A problem may arise in the case of an

environmental sample where the total activity available for analysis is in few dpm range,

Reagent Percent recovery based on PLF surface activity (%)

Percent recovery based on unaccounted activity (%)

3M nitric acid 3.93±4.00 N/A 8M nitric acid 9.87±4.18 N/A 16M nitric acid 132.55±20.95 45.64±15.84

DI water 50.03±9.97 19.13±6.26

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which will require the most analyte to be back-extracted to perform reliable analysis. The

nitric acid or DI water back-extraction method will not provide sufficient activity to

perform TIMS analysis for such a sample.

3.6.2 Back-extraction with Isopropanol

One possible method to increase the recovery of plutonium from PLF substrate is

completely extracting plutonium and ligand complex from the polymer matrix.

H2DEH[MDP] is insoluble in water but soluble in organic diluent [37]. With this

information, PLFs were placed in isopropanol bath to completely remove H2DEH[MDP]-

plutonium complexes from the polystyrene structure. Once PLF was removed from the

bath and isopropanol was completely evaporated, white residue was observed in the

bottom of the beaker. Hydrogen peroxide and sodium vanadate were added to samples to

destroy the plutonium complex. Samples were cleaned with anion column

chromatography then electrodeposited on a stainless steel planchet. The plutonium

recovered with isopropanol was similar to one achieved by the concentrated nitric acid.

Table 3-9 shows percent plutonium recovered by the isopropanol method. PLF surface

based activity recovery calculation showed over 100% recovery, which again confirms

that plutonium had penetrated through the depth of the PLF and deposited under the

surface. The percent plutonium recovery was readjusted based on the PLF surface and

unaccounted activity. The isopropanol back-extraction was less effective than expected.

Since isopropanol would have removed the entire plutonium-ligand bonds from polymer

structure, it was theorized that the low back-extraction was caused due to ineffectiveness

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in breaking bond between plutonium and ligand. The improvement can be made by

utilizing more aggressive chemical method. However, it would be more time consuming

and complicated than the current procedure. It was decided to focus on establishing TIMS

analysis process for the back-extracted samples since both concentrated nitric acid and

isopropanol methods provide enough plutonium activities to perform mass spectroscopy

analysis.

Table 3-9 Plutonium back-extracted from H2DEH[MDP] PLF using isopropanol

3.6.3 TIMS Analysis

Selected samples from the extraction studies were further analyzed with Thermal

Ionization Mass Spectrometry (TIMS) to investigate feasibility of performing plutonium

isotopic measurements. Four samples from the nitric acid experiment and eight samples

from the isopropanol samples were selected for TIMS analysis. For nitric acid experiment

samples, only 239Pu was added to the samples and 242Pu tracer was used to measure the

yield from the process. 240Pu and 239Pu were used in samples from the isopropanol

experiment. 240/239Pu samples were also traced with 242Pu. The 240/239Pu ratio was

controlled from 4 to 27% as shown in Table 3-10.

Reagent Percent recovery based on PLF surface activity (%)

Percent recovery based on unaccounted activity (%)

Isopropanol 129.60±9.15 32.51±2.11

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Table 3-10 240/239Pu isotopic ratio for each samples

Sample ID 240/239Pu Ratio (%) Isopropanol-A 4.37 Isopropanol-B Isopropanol-C 8.81 Isopropanol-D Isopropanol-E 17.78 Isopropanol-F Isopropanol-G 26.71 Isopropanol-H

Each sample was cleaned using the Bio-rad AG® MP-1 resin. Samples were

processed with perchloric acid to eliminate any organic matter that may pass through the

resin bed. Samples were electrodeposited on a degassed zone-refined rhenium filament.

These filaments were loaded on a 20 slot sample turret shown in Figure 3-19. Once

samples were loaded on the TIMS system, filament was ramped up to 1450 oC to ionize

plutonium.

All samples analyzed with TIMS had low background and showed that the

procedure was adequate to process PLF samples. Sample cleanup process was effective

in removing any organic and inorganic compounds that may have presented in the

sample.

Figure 3-19 (A) TIMS turret with triple-filament (B) TIMS sample turret in chamber

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As expected, almost no 240Pu was measured from samples back-extracted by nitric acid.

Samples that were back-extracted with isopropanol all showed presence of both 239Pu and

240Pu. The 240/239Pu ratio measured with TIMS were accurate when compared to the

known values as shown in Figure 3-20.

Figure 3-20 Comparison of TIMS 240/239Pu isotopic ratio measurements from back-extracted samples and known values

TIMS analysis for PLF samples are time consuming process due to the back-

extraction and column chromatography. The entire process takes at least 3 to 4 days to

complete. One way to decrease total analysis time is by directly placing PLF on a TIMS

filament without chemical processing. In the sample preparation, section of the PLF will

be removed from substrate and directly mounted on a filament as shown in Figure 3-21.

This will shorten the total analysis time and at the same time may also provide

enhancement in analyte ionization potential. The thermal ionization efficiency of

plutonium is extremely low. The best reported ionization efficiency for plutonium is 1-

2% [45]. One of way to improve plutonium ionization efficiency is to use additive, such

0

5

10

15

20

25

30

0 1 2 3 4 5

240/

239 P

u ra

tio (%

)

Sample

PLF TIMS

Mass

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as graphite. The additive increases the work function of the metal filament, which

effectively increases the ionization potential. The work function of carburized rhenium is

about 0.4 eV higher than the pure rhenium [46]. H2DEH[MDP] and polystyrene are

mainly consisted of carbon and hydrogen. With large population of carbon atoms, it is

possible to have ligand and/or polystyrene greatly improve a thermal ionization

efficiency of plutonium.

Figure 3-21 Illustration of PLF direct sample mounting on TIMS filament

With the current PLF design, directly mounting a sample on a TIMS filament is

inadequate due to the possibility of iron residue from stainless steel substrate interfering

with the TIMS signal. So instead of removing PLF from substrate and mounting onto a

filament, two approaches were taken to validate compatibility of ligand and polystyrene

with TIMS analysis. The first approach was coating PLF directly onto the filament, then

stippling the plutonium tracer solution onto the PLF to test the effect of the polystyrene

and ligand on the TIMS signal. This first approach will be called the ligand-polymer

method. The second approach was complexing plutonium with H2DEH[MDP] ligand

then stippling the solution on filament. This approach will be called the ligand complex

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method. The second method would eliminate polystyrene from the process and only test

H2DEH[MDP] ligand’s role in TIMS process. This was intended as a surrogate samples

to represent isopropanol back-extracted Pu-ligand complex directly deposited on filament

without column chromatography process. The optical microscopic views of the filaments

from the two methods are shown in Figure 3-22.

Figure 3-22 TIMS filament prepared with (A) ligand-polymer method (B) ligand complex method

TIMS filaments for ligand-polymer method were prepared by stippling 1 µl 1:20

H2DEH[MDP] PLF stock solution directly onto a rhenium filament. PLF coatings

solidify and are ready for the use within few hours of stippling. Once the PLF filament

was ready to use, 1 µl of plutonium standard was stippled onto the filament and air dried.

Two plutonium standards were used and information is given in Table 3-11. The ligand

complex method samples were prepared with same plutonium standard as the ligand-

polymer samples. The standard solution was first dried then re-dissolved in 0.01M nitric

acid and H2DEH[MDP]-isopropanol solution. Samples were left for two hours to form

Pu-ligand complexes then transferred onto rhenium filaments. Both type of samples were

run the same way as the standard electrodeposited samples.

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Table 3-11 Information of plutonium standards used in TIMS analysis Standard 1 Standard 2 Certification agency New Brunswick Laboratory National Institute of

Standard & Technology Certification number CRM 128 SRM 4334G Radionuclides 239Pu and 242Pu 242Pu Atom ratio 0.9993±0.0002 (239Pu/242Pu) NA

TIMS data showed several deficiencies with the new sample preparation methods.

The ligand complex samples did not run well and showed very low counts. Plutonium

isotopic measurement could only made on few samples due to generally low counts.

Plutonium was not effectively transferred to the filament with this technique. Only a few

µl of solution was used to prepare each sample and solution volume seems to be too

small to effectively form ligand-plutonium complexes. This deficiency may be eliminated

by increasing the overall solution volume used to increase change of ligands to form

complexes with analyte. A longer equilibration time with slight agitation could also help

with the formation of complexes.

Figure 3-23 TIMS spectrum from 242Pu sample prepared by ligand-polymer method

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The ligand-polymer samples consistently showed good and stable signal.

However, the background was consistently high at each mass number as shown in Figure

3-23. This behavior is unexpected and unusual. Normally the background is consistently

high in the entire spectrum and not just at each mass number. This behavior was not

observed with the ligand complex samples, which do not contain polystyrene. Also,

conventional electrodeposited samples did not show any background issue, which means

that plutonium standard was not the issue. These samples were prepared in a clean room

and sample contamination was not the cause of the background. This is a good indication

that polystyrene is causing the background issue during the ionization process.

3.7 H2DEH[MDP] PLF Conclusions

H2DEH[MDP] PLFs were effective in plutonium and uranium extraction. 1:10,

1:15, and 1:20 PLF showed similar plutonium extraction behavior. Since 1:20

H2DEH[MDP] PLF was most cost effective, most experiments were performed with 1:20

PLFs. Close to 50% of plutonium was extracted on the surface of 1:20 PLF with 1M

nitric acid. It is important to point out that H2DEH[MDP] PLFs were consistently

susceptible to plutonium penetrating and depositing below the surface. The internal

radiation within the body of PLF did not cause a noticeable degradation in alpha spectra.

The analyte penetration issue was beneficial in the TIMS analysis. Plutonium was

successfully back-extracted from PLF with DI water, concentrated nitric acid, and

isopropanol. The isopropanol removed H2DEH[MDP]-plutonium complexes from

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polymer structure and showed best back-extraction ability. TIMS analysis was completed

without any issues and the isotopic measurement was accurate. TIMS analysis for PLF

samples are time consuming process due to back-extraction and column chromatography.

The entire process takes least 3 to 4 days to complete. One way to shorten the time was to

directly mounting PLF onto the filament. Preliminary studies showed that direct

mounting has great potential to be utilized in TIMS analysis. Further studies are required

to fine tune the method to be effective.

H2DEH[MDP] PLF showed consistency similar to the electrodeposited samples.

The overall analyte recovery was lower than electrodeposited samples. However, PLF is

designed to be a rapid field deployable screening technique and consistency is more

important than the recovery. H2DEH[MDP] PLFs were also tested with unknown activity

samples and confirmed that the PLF system can be effectively used to process unknown

samples.

H2DEH[MDP] PLF was capable of co-extracting or selectively extracting

plutonium over uranium depending on the PLF composition. With 1:5 PLF, about 23% of

plutonium and 20% uranium were simultaneously extracted with 1M nitric acid. 1:10 and

1:20 PLFs preferably extracted plutonium over uranium with 1M nitric acid. The uranium

alpha spectra peaks were well separated from plutonium peaks, and it was possible to

perform isotopic measurements.

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4. Chapter 4

Di(2-ethylhexyl) phosphoric acid (HDEHP)

4.1 Introduction

Di(2-ethyl hexyl) phosphoric acid (HDEHP) ligand based PLF were studied for

plutonium and uranium extraction in various conditions. Samples prepared in the

experiment were examined using alpha spectroscopy and thermal ionization mass

spectroscopy (TIMS) to measure analyte content in the PLF. Digital autoradiography

technique was also used to study distribution of plutonium on the PLF surface. PLFs

were effective in plutonium extraction but generally ineffective for uranium in conditions

tested.

4.2 Theory and Background

HDEHP is an effective metal extractant. It has very efficient chelating properties

for a wide variety of metal ions. HDEHP is an amphiphillic molecule with two long

hydrocarbon chains and a polar end with a phosphoryl oxygen (P=O) and an acidic –OH

group as shown in Figure 4-1 [47].

Figure 4-1 Chemical structure of HDEHP

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HDEHP can be easily synthesized by reacting phosphorus pentoxide with 2-ethylhexanol

to produce a mixture of mono, di, and tri phosphates. Di(2-ethyl hexyl) phosphoric acid is

isolated from the rest of the phosphates based on solubility. The solubility in water is

highest for mono and lowest for tri phosphates. The order of solubility is opposite for

nonpolar solvents [48].

4𝐶8𝐻17𝑂𝐻 + 𝑃4𝑂10 → 2[(𝐶8𝐻17𝑂)𝑃𝑂(𝑂𝐻)]2𝑂

[(𝐶8𝐻17𝑂)𝑃𝑂(𝑂𝐻)]2𝑂 + 𝐶8𝐻17𝑂𝐻 → (𝐶8𝐻17𝑂)2𝑃𝑂(𝑂𝐻) + (𝐶8𝐻17𝑂)𝑃𝑂(𝑂𝐻)2

HDEHP has two metal extraction mechanisms. The first mechanism involves an

ion-exchange between H+ and metal ions. In this process, HDEHP loses the H+ ion and

form a conjugate base. A sufficient number of these extractant anions come together to

form a complex with a metal cation [49]. This process is a dominating extraction

mechanism at the low acidity condition [50]. The second mechanism utilizes a

phosphoryl oxygen group to form a complex with the metal cation. The P=O group has a

strong electron donor and it is in a sterically favorable position to form a metal complex

[49]. This P=O extracting mechanism is the main process to extract metal in the high

acidity condition [50].

HDEHP has shown effectiveness in extracting lanthanides, selective actinides,

and other trivalent elements [49]. Several authors have reported that lanthanides and

elements with +3 oxidation state have similar extraction behavior in nitric acid [50]–[52].

The distribution ratio for lanthanides rapidly decreases at lower nitric concentration then

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start to increase at higher concentration as shown in Figure 4-2 [50], [51]. The trivalent

americium, curium, and yttrium exhibit similar trend as trivalent lanthanides [53]. This

extraction trend can be also observed from hydrogen chloride solution [54]. The

distribution ratio plot shown in Figure 3-1 was generated based on Svantesson’s

empirical equations, which shows good agreement with experimental data [50].

Plutonium and uranium distribution ratios are less dependent on the nitric

molarity than trivalent elements. The dependency is linear with negative slope as shown

in Figure 4-2. For plutonium, it had been reported that HDEHP has high affinity to both

trivalent and pentavalent plutonium [55].

Neptunium extraction by HDEHP has a unique dependency on nitric acid

concentration. The behavior is believed to be a result of neptunium oxidation state change

due to the change in solution acidity. Np(IV) and Np(VI) have very high affinity to

HDEHP. However, Np(V) has low extractability by HDEHP. Pentavalent neptunium is a

dominating specie in a high acidity solution. As the acidity of the solution decreases,

Np(V) is converted to Np(IV) and Np(VI), which in turn leads the distribution ratio to

increase rapidly.

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Figure 4-2 HDEHP distribution ratio dependency on HNO3 concentration for various ions [50]

4.3 Plutonium and Uranium Extraction

HDEHP PLF analyte extraction behavior was tested over various conditions. The

set of experiments performed for HDEHP PLF was similar to H2DEH[MDP] based PLF.

The analyte extraction by HDEHP is well known in liquid/liquid and in resin bead

extraction condition. However, there is a great possibility that extraction behavior is

completely different for the PLF form. In case of H2DEH[MDP] based PLF (which was

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examined in Chapter 3) the PLF analyte extraction behavior is noticeably different from

one observed from liquid/liquid or resin bead based extraction.

4.3.1 Analyte Extraction Characterization

Four different composition HDEHP PLFs – 1:2, 1:5, 1:10, and 1:20 – were

prepared and tested for plutonium extraction over 0.01 to 8M nitric acid solution to

establish the baseline behavior. Different ratio PLFs showed significantly difference in

color as shown in Figure 4-3. 1:10 and 1:20 were both clear with no visual difference

between two. 1:5 PLF was mostly clear but it had opaque colored spot. The entire surface

of 1:2 PLF was opaque in color and it was noticeably soft compare to other ratio PLFs.

1:2 PLF visibly had rough surface and it was easily damaged during sample handling.

239Pu solutions used in this study were prepared with 0.01, 0.1, 1, or 8M nitric acid

solution. The PLF testing procedure was same as the procedure used for H2DEH[MDP]

PLF. 2.5 to 3mL of nitric acid concentration adjusted 239Pu tracer was stippled on the

PLF surface and equilibrate time of 3 hours were used.

Figure 4-3 HDEHP ligand based PLFs

The plutonium recovery by HDEHP PLF was dependent on both nitric acid

concentration and ligand to polymer ratio. 1:2 PLF consistently had the highest recovery

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in nitric concentration examined in this experiment followed by 1:5 as shown in Figure

4-4. It should be noted that spectra from 1:2 ratio PLFs consistently had long tailing and

the ROI for the plutonium peak had to be increased to encompass total counts from the

tracer. 1:10 and 1:20 PLFs had close to zero percent recovery in all nitric acid

concentration except for 0.01M. The highest plutonium recovery was observed in 0.1M

nitric acid for both 1:2 and 1:5 ratio PLFs.

Figure 4-4 The baseline performance of HDEHP PLF in plutonium extraction as a function of nitric acid concentration

The alpha spectrum resolution was quantified by measuring Full Width at Half of

the Maximum (FWHM) using Bortels’ equation. The tailing component of the peak was

also measured along with FWHM. The tailing term combined with the resolution

represented the total broadness of a peak. The peak resolutions and tailing measurements

for 0.1M nitric acid solution samples are given in Table 4-1.

0.00

10.00

20.00

30.00

40.00

50.00

60.00

70.00

80.00

0.01 0.1 1 10

Reco

very

(%)

Nitric Acid (M)

1:2

1:5

1:10

1:20

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Table 4-1 Alpha spectra resolutions and tailing terms for HDEHP PLFs PLF ratio FWHM (keV) Tailing 1:2 7.85±2.95 305.19±5.84 1:5 15.86±0.67 18.65±0.51 1:10 12.37±2.43 22.10±2.40 1:20 12.74±1.62 24.72±1.48

At a glance, the data from Table 4-1 seems to indicate that the 1:2 ratio PLF

sample has the best resolution among the HDEHP PLFs. However, it is important to note

that the spectrum of 1:2 PLF was not conforming to the typical alpha spectrum. The

Bortels’ equation was not designed for such an uncommon peak shape, and there was

large uncertainty in the peak fitting. Also, it must be noted that the tailing term from an

alpha spectrum is as important as the resolution in analyzing the spectrum. The tailing

term for 1:2 is extremely large compared to other PLFs as shown in Figure 4-5. This

indicates that alpha spectrum from 1:2 ratio PLF is too broad to be effectively used in any

meaningful analysis. A large tailing term from 1:2 PLF is a possible indication that large

amount of ligands present in the film reduced the smoothness of the surface as compared

to the other PLFs. A rough surface is known to cause source attenuation in an alpha

source, which leads to degradation in spectrum. Also, it can be noted that the 1:2 ratio

PLF surface was not as rigid as the other ratio PLFs, and it was prone to scratching

during sample handing. The resolutions and tailing terms for the other three PLFs were

similar to each other and comparable to the electrodeposited alpha sources. This is a good

indication that the source attenuation in 1:5, 1:10, and 1:20 PLFs are minimal and

suitable for alpha spectroscopy.

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Figure 4-5 Alpha spectra for 1:2 (blue) and 1:5 (red) PLFs

Based on the alpha spectroscopy resolution and recovery, 1:5 HDEHP PLF was

the best candidate to be used in plutonium separation from 0.1M nitric acid. The main

reason that different ratio PLFs provided different recovery is due to the number of active

sites available on the surface for plutonium. The active sites were less on 1:10 and 1:20

PLFs than either 1:2 or 1:5 PLFs, and plutonium recovery was expected to be affected by

the amount of ligand in PLF. However, it was not expected to see significantly drop off in

plutonium recovery from 1:5 PLFs to 1:10 and 1:20. All four PLFs examined should have

provided enough ligands to extract plutonium from the solution. Based on the plutonium

extraction behavior, it was theorized that there is some kind of interaction between ligand

and polystyrene that cause the orientation of ligands to change based on ligand to

polymer ratio. The orientation of ligands in 1:2 and 1:5 ratio PLFs are clearly more

favorable for plutonium extraction than in 1:10 and 1:20 ratio PLFs. Another possible

exploration of such an extraction behavior is that the low amount of ligand in the

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polystyrene may have caused most of the ligands to be entangled in the bulk polymer

structure and only a trace amount to be present on the surface for the extraction.

Since the first experiment was coarse with range gap between the data points, a

more detailed experimentation was carried out based on the initial data. PLFs were

prepared with small ratio increments over and under the 1:5 PLF and tested for plutonium

extraction. Total of four new PLF compositions were prepared: 1:3, 1:4, 1:6, and 1:7.

These ratios were selected to provide finer detail between 1:2 and 1:5 and between 1:5

and 1:10 to see whether the change in plutonium extraction is a sudden or gradual

change.

1:6 and 1:7 PLFs showed slight improvement in plutonium extraction over 1:10 or

1:20 PLF in all nitric acid concentration as shown in Figure 4-6. The plutonium

recoveries were still low, below 10%, even with increase in HDEHP ligand in PLF. Both

1:3 and 1:4 PLFs had similar spectrum tailing issue observed in 1:2 PLF. Alpha spectrum

ROI was adjusted accordingly to encompass entire counts from 239Pu. The long peak

tailing is undesirable in alpha analysis due to possible peak convolution caused by the

tail. For the case of 1:3 and 1:4 PLFs plutonium recoveries generally fall between 1:2 and

1:5 in all nitric acid concentration except for 0.1M as shown in Figure 4-7. In 0.1M nitric

acid, 1:5 still had higher plutonium recovery than either 1:3 or 1:4 PLF.

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Figure 4-6 Plutonium recovery by 1:6 through 1:20 HDEHP PLF as a function of nitric acid concentration

Figure 4-7 Plutonium recovery by 1:2 through 1:5 HDEHP PLF as a function of nitric acid concentration

The plutonium recoveries were plotted as function of PLF ratio in Figure 4-8 to

better show the recovery transition as the function of PLF ratio. There were sudden

plutonium recovery efficiency change from 1:6 and 1:5 PLF. It seems to be that 1:5 is a

transitioning point from low to high recovery. This greatly suggests that ligands have to

reach a certain mass compared to polymer to become available for analyte extraction. The

0.00

2.00

4.00

6.00

8.00

10.00

12.00

14.00

0.01 0.1 1 10

Reco

very

(%)

Nitric Acid (M)

1:6

1:7

1:10

1:20

0.00

10.00

20.00

30.00

40.00

50.00

60.00

70.00

80.00

0.01 0.1 1 10

Reco

very

(%)

Nitric Acid (M)

1:2

1:3

1:4

1:5

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behaviors were similar for all three nitric acid concentrations shown in Figure 4-8. In

0.01M and 1M nitric acid, percent plutonium recovery reached a plateau at between 1:3

and 1:4 before achieving highest plutonium recovery with 1:2 PLF. In 0.1M nitric acid,

however, plutonium recovery spiked at 1:5 PLF then significantly decreased at 1:4 PLF.

Plutonium recoveries then start to linearly increase from 1:4 to 1:2 PLF.

The 1:5 PLFs consistently had large standard deviations with 0.1M nitric acid.

The standard deviation could be result of a number of different issues. The first

possibility is due to inconsistency in PLF composition. The 1:5 PLF is right at the

transition point and slight change in ratio may dramatically change the plutonium

recovery. The second possibility is due to inconsistent plutonium states in the tracer

solution used in the experiment. Plutonium oxidation state issue was already discussed in

Chapter 3.

Figure 4-8 Plutonium recovery by HDEHP PLF as function of PLF composition

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Some of the PLFs were also tested for penetration of plutonium through the depth of the

polymer film. It has been shown in H2DEH[MDP] PLF that plutonium was capable of

penetrating and depositing below the surface. Tracer solutions that were left on PLF were

collected and electrodeposited to measure any unaccounted plutonium activity. The

unaccounted plutonium activities shown in Figure 4-9 indicate that plutonium had

potentially deposited through the body of PLF.

Figure 4-9 Unaccounted plutonium by H2DEH[MDP] PLF as function of nitric acid concentration

4.3.2 Analyte Extraction Time Dependency

An analyte extraction time study was performed with 1:5 HDEHP PLFs and 0.1M

nitric acid solution. PLFs were tested with exposure time from 10 to 180 minutes. The

extraction conditions were kept consistent throughout the experiment except for the

exposure time. The plutonium recovery linearly increased from 10 to 60 minute exposure

time then slightly dipped for 90 and 120 minute exposure before the maximum recovery

was achieved at 180 minutes. Recoveries from 60 to 120 minutes were, however, all

0

10

20

30

40

50

60

0.01 0.1 1 10

Pu re

cove

ry (%

)

Nitric concentration [M]

1:3

1:4

1:5

1:6

1:7

1:10

1:20

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within standard deviation of measurements. The HDEHP PLF analyte extraction

dependency on time was similar to one observed with 1:20 H2DEH[MDP] PLF. The

plutonium recovery by HDEHP and H2DEH[MDP] PLFs function of exposure time is

plotted in Figure 4-10. Student’s t-test was performed to confirm and assess the statistic

difference between plutonium recoveries between 60 to 180 minutes. The recoveries

measured at 60 and 120 minute exposure time were statistically indifferent from the 180

minute measurement at 95% confidence level. However, 90 minute plutonium recovery

was statistically different than 120 minute recovery based on student’s t-test.

Figure 4-10 HDEHP and H2DEH[MDP] PLF plutonium recoveries at different exposure time

The plutonium recovery dependency shown in this study provides flexibility in

deploying this technique in emergency response. Based on the sample type, the

equilibration time can be changed to best suit the particular sample. For example,

samples with high activity can be rapidly processed since HDEHP PLF was capable of

extracting 10% of plutonium from nitric acid even at 10 minutes. Depending on the initial

0

10

20

30

40

50

60

70

0 30 60 90 120 150 180

Pu re

cove

ry (%

)

Time (min) HDEHP H2DEH[MDP]

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sample activity, 10% recovery may provide enough activity for alpha spectroscopy. Even

for the sample with low activity, a 10 minute exposure time would most likely provide

enough activity for mass spectroscopy analysis. As mentioned before in Chapter 3, about

100 femtogram of plutonium is needed for reliable TIMS analysis. In any conceivable

post-detonation situation, the mass of plutonium in the sample collected near the ground

zero will be significantly higher than 100 femtogram.

4.3.3 Consistency Study

The consistency of HDEHP PLFs was examined by preparing and testing two

batches of 1:5 PLF with 0.1M nitric acid solution. The data from the previous

experiments showed a large standard deviation from 1:5 PLFs that were tested with 0.1M

tracer solution. This high deviation could have been a result of either PLF variation or

oxidation state difference in solutions used. In this experiment, a single plutonium tracer

solution was used for both batches to eliminate possibility of plutonium oxidation states

playing role in extraction behavior. This ensured that any plutonium recovery variation

would be caused by the variation in PLF itself.

Stock solutions were prepared on different dates and PLFs were also synthesized

on different dates. The amounts of each PLF component used in the stock solutions are

listed in Table 4-2. The weight ratio between ligand and overall mass was kept as close as

possible to minimize difference in two PLF batches. PLFs from both batches were

prepared with solvent cast method. Once PLFs were prepared and ready for the

experiment, the appearance of both batches was compared. The first batch was more

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opaque and second batch was mostly clear with small opaque spot. As shown in Table

4-2, difference between PLF compositions was minimal. The small difference in

composition of these PLFs is not great enough to explain the discrepancy.

Table 4-2 Mass of components used to prepare two HDEHP PLF batches for consistency study Batch 1 Batch 2 HDEHP (g) 1.402 1.423 Polystyrene (g) 5.589 5.647 THF (g) 28.119 28.954

Two batches and these stock solutions were prepared on different dates. The major

difference between two batches was the time spent on outgassing THF from the polymer

structure. Both stock solutions were left to dissolve polystyrene for 3 days before

preparing PLF. The first batch was out gassed for 30 days before using in the study

compared to only 2 days for the second batch.

PLFs were tested to check whether the physical appearance has any effect on the

plutonium recovery. Six PLFs were selected from each batch and tested on same date

using freshly prepared 239Pu tracer in 0.1M nitric acid. The experiment condition was

same for both batches. Each sample was counted in six different alpha counters for two

reasons. First, it was to ensure fidelity of PLF in multiple sample counting. Second, it

was performed to measure activity variation introduce by the different counting systems.

Since radiation decay is a stochastic process, there will be slight difference in activity

each time sample is counted. The activity variation due to the counter should be minimal

and lower than variation caused by PLF itself.

Plutonium recoveries were significantly different between the batches. PLFs from

first batch had consistently higher recoveries than the PLFs from second batch. The entire

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count data is plotted in Figure 4-11 and mean plutonium recovery from each batch is

shown in Table 4-3.

Figure 4-11 Plutonium recoveries by 1:5 HDEHP PLFs with 0.1M nitric acid solution

The average plutonium recovery from first batch was about three times higher than the

one from second batch. As mentioned before, a small difference in composition of these

PLFs is not great enough to explain for the discrepancy. More plausible explanation

would be that the recovery discrepancy would have been due to an entrapment of THF in

polymer structure. The possibility of THF entrapment was discussed in Chapter 2 and it

is possible that a large amount of THF was still remaining in PLFs from the second batch.

Table 4-3 Average plutonium recovery by HDEHP PLF batches First Batch Second Batch Overall Detector 1 32.28±5.39% 11.08±5.05% 19.03±11.03% Detector 2 30.51±5.43% 9.98±4.86% 18.73±11.07% Detector 3 32.64±6.20% 10.58±4.66% 20.04±11.98% Detector 4 30.12±4.82% 9.68±4.31% 18.47±10.92% Detector 5 31.22±5.44% 9.62±4.51% 18.82±11.45% Detector 6 32.39±4.93% 9.75±4.08% 19.40±11.72%

0.00

5.00

10.00

15.00

20.00

25.00

30.00

35.00

40.00

45.00

0 1 2 3 4 5 6 7 8 9 10 11 12 13

Plut

oniu

m R

ecov

ery

(%)

Sample #

Detector1

Detector2

Detector3

Detector4

Detector5

Detector6First Set Second Set

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It is theorized that the difference in the color for both batches were caused by

unevaporated THF. Also, the color of second batch PLFs changed after counting under

the vacuum condition. There was no noticeable difference in two batches in appearance

as shown in Figure 4-12. Placing samples under the vacuum may have evaporated the

THF out of the polymer structure. The effect of THF on the analyte recovery mechanism

was not fully understood but it is the most likely cause of the low analyte recovery in

second batch.

Figure 4-12 Comparison of two HDEHP PLF batches after alpha counting

The effect of THF in analyte recovery was studied by further testing PLFs from

the second batch. The focus of this experiment was to remove THF from PLF matrix then

test PLF for plutonium extraction to quantify effect of THF on the recovery. PLFs from

second batch were left on bench top to further outgas the solvent from the polymer

matrix. After 16 days of outgassing, which was 13 days longer than PLFs used in

consistency experiment, six PLFs were selected for the experiment. All six PLFs were

opaque and similar to first batch PLFs tested for plutonium extraction. These PLFs were

divided into two groups: the first group was heat treated by placing it in a furnace for an

hour to boil the THF out of the polymer and the second group was used without further

First Set Second Set

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processing. PLFs from two groups showed significant visual difference as shown in

Figure 4-13. PLFs that were heat treated became clear with no opaque spots. Whereas

unprocessed PLF was just opaque.

Figure 4-13 1:5 HDEHP PLF (A) after heat treatment (B) after 16 day outgassing

PLFs were tested with the standard plutonium extraction procedure. Each sample was

counted once and data was compared with the data from the consistency study. Both heat

treated and outgassed PLFs showed great improvement in plutonium recovery over the

second batch PLFs. The heat treated PLFs, however, showed long peak tailing in its alpha

spectrum. The ROI in the counting software was increased accordingly to account for the

long tailing. The tailing indicated that THF had damaged the surface while evaporating

and caused self-absorption on the surface. The spectra are plotted in Figure 4-14 to

compare the resolution and tailing.

Table 4-4 Plutonium recovery improvement after outgassing and heat treatment Heat Treated Air Dried First Batch* Second Batch* 32.27±3.10% 27.16±7.40% 31.53±5.08% 10.11±4.28%

*Average plutonium recovery was calculated using data from all six detectors

The improvement in plutonium recovery is a good indication that THF plays a role in

analyte recovery. It is essential to effectively remove THF from PLF. The best approach

to the THF issue is to air dry PLF for longer duration. Plutonium recovery was improved

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by air drying PLF for 13 extra days without any adversary effect on spectrum resolution.

Thermally evaporating THF showed greater improvement in plutonium recovery;

however, thermal process introduced source attenuation in sample spectrum.

Figure 4-14 Alpha spectra comparison between heat treated HDEHP PLF (blue) and air dried PLF (red)

It is important to further discuss the color difference observed from 1:5 HDEHP

PLFs used in the experiment. The color difference between first and second batch PLFs

was believed to be a result of the different length time used to outgas THF from the PLFs.

A PLF was closely observed over 12 day period after the preparation to record the

changes in color. The PLF was mostly clear initially with some white spots. The gradual

change was, however, obvious as time goes on as shown in Figure 4-15. By the 9th day

after preparing PLF, entire surface became opaque without any clear portion. There was

no change in PLF observed after 9th day. It is believed that after 9 days of outgassing,

PLF is stabilized and no further unforced evaporation of THF is occurring.

0

50

100

150

200

250

300

4800 4850 4900 4950 5000 5050 5100 5150 5200

Coun

ts

Energy (keV)

Resurfaced

Outgassed

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Figure 4-15 1:5 HDEHP PLF surface color progression over 12 days

The heat treatment of PLF also has shown to cause change in PLF color as shown in

Figure 4-16. The color change in heat treated PLF was more carefully studied by

monitoring PLF over 12 days after the heat treatment. The heat treated PLF becomes

clear initially then within few hours start to develop opaque sports. The opaque spot was

only developing along the edge for first day then spots started to appear at the center of

PLF. Figure 4-16 is showing the progression of spots developing on the PLF. By the 12th

day after the heat treatment, entire surface started to show white tint.

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Figure 4-16 Heat treated 1:5 HDEHP PLF surface color progression over 12 days

4.3.4 Alternate PLFs

The 1:5 HDEHP PLFs prepared by spin coating method were tested for plutonium

extraction. The 1:5 PLFs were totally clear without any white spots, which is a clear

difference from the solvent casted PLFs. The spin coating removed any excess PLF

solution and only about 12 mg of material was coated on the stainless steel substrate.

PLFs were tested for plutonium extraction with the standard method to compare against

solvent cast PLF. The plutonium recovery on the PLF surface was lower than one

achieved with the solvent casted PLF. Only 19% of plutonium was recovered compared

to 49% with solvent casted PLF. The main issue with the spin coated PLFs was the

tailing in the alpha spectrum, which indicates sample attenuation. Figure 4-17 is a

comparison of spectra from solvent casted PLF and spin coated PLF. The spectrum from

spin coating clearly showed a longer left hand tailing than the solvent casted PLF.

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Figure 4-17 Alpha spectra comparison between for heat treated 1:5 HDEHP and regular PLFs

The degradation of alpha spectrum is likely to be a result of the thin profile of the film.

Plutonium was deposited on both the surface and the body of the PLF. The alpha decay

energies from plutonium that deposited in the body of PLF were losing energy as it

escaped the PLF.

The spray coated HDEHP PLFs were not examined for plutonium extraction.

Spray coated PLFs had rougher surfaces and normally suffer from resolution degradation

issue based on H2DEH[MDP] data from Chapter 2. The degradation issue worsen with

the spray coating method and this method will not provide any advantage over solvent

casting or spin coating method to warranty any further investigation.

4.4 Surface Characterization

The surface characterizations of HDEHP PLFs were performed with Scanning

Electron Microscope (SEM) and digital autoradiography. All the surface characterization

studies were performed with the solvent casted PLFs. SEM was used to see any

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microscopic defects on the PLF surface, and digital autoradiography was used to image

the distribution of plutonium. SEM analysis revealed presence of defects on all PLF

samples examined as shown in Figure 4-18. Images were taken at different

magnifications to show the types of defects that were presented on the PLF surfaces.

Thus, a direct comparison could not be made. The origin of these defects could not be

explicitly determined, but some of the defects appeared to be generated during sample

handling. As mentioned before, the 1:2 ratio PLF surface was not rigid and was prone to

scratching during handling. Types of defects observed in the 1:2 PLF resemble scratches

that may have been created after the film was formed. Based on the alpha spectroscopy

data, it seemed that the surface defects played no major role in plutonium recovery.

Figure 4-18 SEM images for different ratio HDEHP PLFs

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Radiography images of samples were collected to study the plutonium distribution

on the PLF surface. 1:2 and 1:5 PLFs were used in the plutonium distribution study. The

digital radiography image in Figure 4-19 shows that the distribution was not uniform on

the PLF surface. There seems to be hot spots along the edges and in the center of the

samples. The digital autoradiography image shown in Figure 4-19 was imported and

analyzed with the particle distribution software. Six samples were all processed and it all

showed uneven distribution as shown in Figure 4-20 and Appendix C. The location of hot

spots were unique to each sample but it was confirmed to be mostly along the edge and in

center of PLF by the particle distribution software. The analyte distributions trend was

indifferent between two PLF compositions examined.

Figure 4-19 Digital autoradiography image of 1:2 and 1:5 HDEHP PLFs

The plutonium distribution on HDEHP PLFs were different than ones observed

with H2DEH[MDP] PLFs. Hot spots along the edge was unique to HDEHP PLFs. Since

ligand is the only component within the PLF that had shown any affinity to plutonium,

the particle location map can be interpreted as a ligand locational map. Conglomeration

of HDEHP along the edge would most likely have happened during the PLF preparation

1:2

1:5

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process. Another possible explanation of the highly localized distribution is that defects

on the surface were increasing the overall size of area available for the analytes. HDEHP

ligands were not only on the surface but on the entire body of PLF. The defects or

damages on the surface are exposing ligands that would have normally been below the

surface. Once the ligand is exposed, it has a higher chance of extracting an analyte and

the location is captured on the digital autoradiography image.

Figure 4-20 Plutonium distribution map of HDEHP PLF generated from digital autoradiography image

4.5 Uranium Analysis

HDEHP ligand also has a high distribution ratio for uranium. HDEHP PLFs tested

for uranium extraction with the standard extraction procedure. The only modification to

the procedure was to the tracer solution; natural uranium was used as the tracer instead of

239Pu. 1:2 PLF was excluded from uranium study due to the sample attenuation issue

observed from plutonium samples. The uranium extraction with HDEHP PLF was

ineffective in all condition tested as shown in Figure 4-21. The maximum uranium

recovery was only slightly higher than 4%. The ineffectiveness for uranium extraction

shown by HDEHP is most likely due to the polymer support structure. The polymer used

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in PLF has no direct affinity to plutonium or uranium; however, it is clearly affecting the

analyte extraction behavior of the ligand. In PLF, ligands were immobilized by the

polystyrene and that had great effect on the analyte extraction behavior.

Figure 4-21 Uranium recovery by HDEHP PLF as function of nitric acid concentration

4.6 Mass Spectroscopy Analysis

A mass spectroscopy experiment was performed in two parts. First back-

extraction of analyte from PLF was studied then possibility of performing TIMS analysis

on back-extracted samples was studied. The main goal of TIMS analysis on PLF sample

was to gain plutonium isotopic information.

-1

0

1

2

3

4

5

6

0.01 0.1 1 10

U re

cove

ry (%

)

Nitric concentration [M]

1:5

1:10

1:20

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4.6.1 Back-extraction with Nitric Acid and Deionized Water

Plutonium back-extraction was first studied with nitric acid and deionized water. HDEHP

ligand showed plutonium extraction dependency on the acidity of the solution. At higher

nitric concentration, HDEHP becomes ineffective for plutonium extraction as shown in

4.3.1 Analyte Extraction Characterization section. Based on this information, 3M, 8M,

and concentrated nitric acid were first examined for the plutonium back-extraction.

HDEHP PLF was individually placed on a 10 mL nitric acid solution bath for 24 hours.

Samples were cleaned using the anion column chromatography then electrodeposited on

stainless steel substrates. These samples were counted with 450 mm2 alpha detectors for

24 hours.

Table 4-5 HDEHP PLF plutonium back-extraction with nitric acid and DI water

Plutonium back-extraction became more effective as the nitric acid concentration

increased. Table 4-5 shows plutonium recovered from PLF with the back-extraction

procedure. The back-extraction trend followed the data collected from PLF experiment

and HDEHP distribution data [17]. In previous data, the ligand becomes less effective in

containing plutonium as nitric acid concentration increases, which was clearly shown in

the nitric acid back-extraction study. The maximum percent back-extraction was higher

than 100% with 16M nitric acid. This is a clear indication that, at least, some of

unaccounted plutonium activity was actually deposited below the surface of HDEHP

Reagent Percent recovery based on PLF surface activity (%)

Percent recovery based on unaccounted activity (%)

3M nitric acid 32.47±4.89 13.96±3.17 8M nitric acid 79.39±12.84 40.85±5.57 16M nitric acid 147.98±13.48 74.25±11.63 DI water 22.31±4.61 8.40±3.82

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PLF. The percent back-extraction calculated based on unaccounted activity was around

74%, which was more reasonable than the percent recovery based on PLF surface

activity.

Deionized (DI) water was also used in same bases of nitric acid. The ligand is

normally used in acidic condition and placing it under DI water has potential to break

ligand to plutonium bonds. The procedure was the same as the nitric acid procedure

except a reagent was changed from nitric acid to DI water. The percent back-extracted

plutonium data is shown in Table 4-5. DI water was not effective in plutonium back-

extraction and higher concentration nitric acid is a better candidate to extract plutonium

from HDEHP PLF.

4.6.2 Back-extraction with Isopropanol

Plutonium back-extraction was effective with concentrated nitric acid. However,

about 30% of plutonium activity were still left on the PLF based on the unaccounted

activity data. It is always advantageous to fully back-extract analyte from PLF to perform

TIMS or any other destructive analyses. One possible method to increase the recovery of

plutonium from PLF substrate is completely extracting plutonium and ligand complex

from the polymer matrix by placing PLF in organic diluent. The organic solvent back-

extraction was successfully performed with H2DEH[MDP] PLF and showed great

improvement in plutonium recovery over nitric acid or DI water methods.

HDEHP PLFs were individually placed in 10 mL isopropanol bath for 24 hours.

Isopropanol was completely evaporated under the fume hood after removing PLF from

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the bath. Hydrogen peroxide and sodium vanadate were used to destroy the ligand-

plutonium complexes. For the final step, samples were cleaned using the anion column

chromatography.

Table 4-6 HDEHP PLF plutonium back-extraction with isopropanol

The plutonium back-extraction with isopropanol was less effective than with the

concentrated nitric acid. The percent plutonium back-extracted from PLF is shown in

Table 4-6. The percent back-extraction was about 40% lower than the one achieved with

the concentrated nitric acid. The back-extraction procedure with isopropanol was more

cumbersome and time consuming than the nitric acid procedure. Since ligand-plutonium

complexes were extracted from PLF, extra steps were needed to break the bond and

samples clean up needed larger column bed size than nitric acid procedure. The

isopropanol would have removed the entire plutonium from the PLF. However, the extra

chemical procedure to break complex bonds is causing the lower plutonium recovery than

the nitric acid method.

4.6.3 TIMS Analysis

PLF samples were prepared with 239Pu and then back-extracted with concentrated

nitric acid. Once analyte was back-extracted from PLF, samples were traced with 242Pu to

measure the yield from the process. The cleanup and TIMS procedure developed with

H2DEH[MDP] PLF was also used to process HDEHP samples. Each sample was cleaned

Reagent Percent recovery based on PLF surface activity (%)

Percent recovery based on unaccounted activity (%)

Isopropanol 83.73±14.41 41.99±20.56

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using the Bio-rad AG® MP-1 resin. Samples were processed with perchloric acid to

eliminate any organic contaminants. Samples were electrodeposited on rhenium

filaments. The cleanup process was effective and all samples analyzed with TIMS had

low background.

Figure 4-22 Comparison of TIMS 239/240Pu isotopic ratio measurements from back-extracted samples and known values

The plutonium isotopic measurements from alpha spectroscopy and TIMS were

compared and plotted in Figure 4-22. Due to the alpha decay energy difference between

239Pu and 242Pu, isotopic ratios were easily calculated from the alpha measurement. The

plutonium isotopic measurements from both techniques were within the standard

deviation of each other. The isotopic ratios measured with alpha spectroscopy had larger

uncertainties compared to TIMS data. The mass spectroscopy measurement uncertainties

were mostly less than 1%.

0

0.02

0.04

0.06

0.08

0.1

0.12

0.14

0 2 4 6 8 10

239/

242 P

u

Sample

Alpha spec

Mass spec

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4.7 HDEHP PLF Analysis Conclusions

HDEHP PLFs were effective in plutonium extraction. 1:5 PLF showed best

combination of plutonium extraction and alpha spectrum resolution from eight different

PLF composition tested. The percent plutonium recovery was slightly lower than 50%. It

is important to point out that HDEHP PLF was also susceptible to plutonium penetrating

and depositing below the surface. The 50% analyte recovery was only based on surface

plutonium activity measured by silicon alpha spectroscopy. The overall plutonium

extracted by the entire body of PLF is estimated to be 80%. The internal radiation within

the body of PLF did not cause noticeable sample attenuation in 1:5 PLF. The analyte

penetration issue could be beneficial in destructive analyses. The extra plutonium

contained in PLF body will give more latitude in the analysis. Plutonium was

successfully back-extracted using concentrated nitric acid and TIMS analysis was

performed. TIMS analysis was completed without any issues and isotopic measurement

was accurate.

HDEHP PLF was surprisingly ineffective for uranium extraction from nitric acid.

PLFs tested with natural uranium tracer showed no significant uranium recovery from

0.01 to 8M nitric acid concentrations. HDEHP ligand is actually effective for both

plutonium and uranium in liquid/liquid and resin bead based extraction. It is believed that

polystyrene structure is causing ligand to behave differently than in other matrixes.

One of the main deficiencies observed from 1:5 HDEHP PLFs was inconsistency

in plutonium recovery shown from different PLF batches. The PLF performance was

greatly affected by the THF encapsulated within the PLF body. The plutonium recovery

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can be successfully increased by air drying THF for longer duration. The thermal

treatment of PLF ensure complete removal of THF, but caused higher surface attenuation,

which caused peak tailing in alpha spectrum.

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5. Chapter 5

Other Ligands

Trialkyl methylammonium chloride (Aliquat-336), 4,4’,(5’)-di-(tert-

butylcyclohexano)-18-crown-6, and 2-ethylhexyl 2-ethylhexylphosphonic acid

(HEH[EHP]) were also studied for analyte extraction in PLF form. All three ligands were

studied for plutonium extraction and 18-crown-6 was also studied for strontium

extraction. These ligands were less effective than H2DEH[MDP] and HDEHP in analyte

extraction. Aliquat-336 and 4,4’,(5’)-di-(tert-butylcyclohexano)-18-crown-6 also showed

inability to withstand high concentration nitric acid.

5.1 Trialkyl methylammonium chloride (Aliquat-336)

Trialkyl methylammonium chloride, also known as Aliquat-336, is a quaternary

ammonium salt widely used for metal extraction. Aliquat-336 mainly contains octyl and

decyl groups with octyl predominating [56]. It is a clear and extremely viscous liquid

with an average molecular weight of 475 [57]. The chemical structure of Aliquat-366 is

shown in Figure 5-1.

Figure 5-1 Chemical structure of Aliquat-336

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Aliquat-336 is reported to aggregate and form micelles in inert diluents and the

aggregation can be reduced by using aromatic diluents or by adding a strong Lewis base

[58], [59]. Aggregates behave like monofunctional species in extraction of metal complex

[60]. The extractions are performed in two mechanisms. Anionic species are extracted as

ion pairs and neutral species are extracted as adducts [59], [61].

Aliquat-336 in resin bead form is an extremely effective extractant for tetravalent

actinides in wide range of acidity [61]–[63]. The distribution ratios for Th(IV), U(IV),

and Pu(IV) are highest at 2-4 M nitric acid. The maximum for Np(IV) occurs at 3-4 M

nitric acid. The tetravalent actinides are extracted as hexanitrato complexes [61].

Figure 5-2 Aliquot-336 distribution ratio dependency on HNO3 concentration for various ions

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The extractant is less effective for hexavalent actinides compared to tetravalent

species. The distribution ratios for Np(VI), U(VI), and Pu(VI) are about 2 orders of

magnitude less than the tetravalent species [63]. The distribution ratio for U(VI) reached

maximum at 6-7 M nitric acid concentration [61]. The extractability of U(VI) started to

decrease at 7 M nitric acid. This is believed to be due to the formation of inextractable

protonated complex H UO2(NO3) [63].

Aliquat-336 is used by Eichrom Technologies, Inc. to manufacture their TEVA®

branded resin. The resin is manufactured by coating the extractant onto a stable polymer

support. The main application for this resin is for separation of technetium and tetravalent

actinides and lanthanides.

5.1.1 PLF Preparation and Testing

Aliquat-336 was selected for a plutonium/uranium separation. PLFs were

prepared with solvent casting method with polystyrene and first tested with nitric acids to

ensure polymer structural agility under the harsh condition. The nitric acid test showed

that Aliquat-336 PLF was structurally unstable to be used with nitric acid. Figure 5-3 was

taken after Aliquat-336 PLF was exposed to the nitric acid. The polymer structure was

completely degraded, and PLF turned into a greenish color. Due to the instability of the

polymer film, Aliquat-336 PLF was not tested for plutonium extraction and no further

investigation was performed. TEVA® resin does not show any incompatibility with high

concentration nitric acid. In fact, the resin performed better for most analytes at high

nitric acid concentrations. The difference in the reaction shown by resin form and PLF

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could be due to different preparation method or different polymer used as a support

matrix. TEVA is manufactured by coating Aliquat-336 onto Amberchrom CG-71ms [64].

Aliquat-336 PLF is prepared using polystyrene and ligand in strongly fixated onto the

polymer structure. Since H2DEH[MDP] PLF has shown ability to separate plutonium

from uranium, no other ligands will be investigated for the Pu/U separation scheme.

Figure 5-3 Aliquat-336 PLF damaged by high concentration nitric acid

5.2 4,4’,(5’)-di-(tert-butylcyclohexano)-18-crown-6 (DtBuCH18C6)

Crown ether was first synthesized by Charles Pedersen in 1967. It is a cyclic

compound that uses its cavity structure to strongly bind to cations [65]. The 18-crown-6

variant of crown ethers is especially effective in strontium separation. The center cavity

of 18-crown-6 is used to extract strontium as illustrated in Figure 5-4 [66]. Cavity size is

the key to analyte extraction.

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Figure 5-4 Strontium 18-crown-6 complex

Dicyclohexyl-18-crown-6 (DC18C6) and its variant 4,4’,(5’)-di-(tert-

butylcyclohexano)-18-crown-6 (DtBuCH18C6), shown in Figure 5-5, have been reported

by several authors to selectively form a strong complex with strontium over many

potential interfering elements [65], [67]–[70]. DtBuCH18C6 showed no ability to extract

Na(I), K(I), Fe(III), Al(III), Ca (II), Cs(I), La(III), Y(III), Ru(III), Mo(VI), and Pd(II)

[65], [70].

Figure 5-5 Chemical structure of (A) DC18C6 (B) DtBuCH18C6

DtBuCH18C6 ligand is also used in resin bead form. The product is commercially

available from Eichrom Technologies as Sr resin. The resin is manufactured by coating

1.0M DtBuCH18C6 in 1-octanol onto an inert chromatographic support. The bed density

of Sr Resin is approximately 0.35 g/mL [71].

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Strontium extraction with DtBuCH18C6 ligand is highly dependent on the nitric

acid concentration [69]. The distribution ratio for strontium increases with increasing

nitric acid concentration. The highest strontium extraction occurs at 8 M nitric solution as

shown in Figure 5-6. The back-extraction of strontium can be performed by using low

concentration nitric acid as distribution ratio rapidly decreases at lower molar nitric acid

solution. DtBuCH18C6 also shows high affinity for Pu(IV) at high nitric acid

concentration. The k’ for Pu(IV) peaks out at 4M as shown in Figure 5-6.

Figure 5-6 DtBuCH18C6 distribution ratio dependency on HNO3 concentration for various ions

5.2.1 Plutonium Extraction

DtBuCH18C6 has shown affinity to plutonium in resin bead form. Based on that

fact, crown ether PLFs were prepared by solvent casting method and tested for plutonium

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extraction. Four different ratio PLFs, 1:2, 1:5, 1:10, and 1:20, were tested with nitric

acids ranging from 0.01 to 8M. The four different PLFs synthesized with DtBuCH18C6

were all clear and there were no visual differences between them as shown in Figure 5-7.

Some of the PLF developed large bubbles along the edge. An equilibration time of 3

hours was used for the experiment.

Figure 5-7 Crown ether PLFs prepared with solvent casting method

All four DtBuCH18C6 PLFs were ineffective in plutonium extraction in the entire nitric

acid concentration ranges tested. The highest plutonium recovery was observed with 1:20

PLF and 0.1M nitric acid. However, the uncertainty was large and recovery was only

around 2.3%. Plutonium recoveries were plotted in Figure 5-8, which clearly show

ineffectiveness of DtBuCH18C6 PLF in plutonium extraction. The tracer solution was

collected and plated after 3 hour equilibration time to measure unextracted plutonium

activity. The PLF and electrodeposition data was computed to calculate unaccounted

activities and plotted in Figure 5-9. The unaccounted activities were consistently higher

than the PLF activities measured from alpha spectroscopy. The unaccounted activities

were relatively consistent from 0.01 to 1M nitric acid for all four ratio PLFs: about 31 to

38% activities were missing. At 8M nitric acid, unaccounted activities from 1:10 and

1:20 PLFs noticeably increased compared to the other nitric acid concentration tested. It

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is suspected that high concentration acid is damaging the PLF and causing polymer

structure to be more porous to the solution. As the polymer medium becomes more

porous, higher amount of plutonium is penetrating through the PLF and deposited below

the surface.

Figure 5-8 Plutonium recovery by crown ether PLF as a function of nitric acid concentration

Figure 5-9 Unaccounted plutonium recovery by crown ether as a function of nitric acid concentration

23

28

33

38

43

48

53

0.01 0.1 1 10

Pu re

cove

ry (%

)

Nitric concentration [M]

1:2

1:5

1:10

1:20

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The damages caused by 8M nitric acid are more noticeable in 1:2 and 1:5 DtBuCH18C6

PLF. The visible damage was significant and samples were not counted with alpha

spectroscopy due to the unstable nature of the PLF. Two data points were excluded in the

plutonium recovery plots in Figure 5-8 and Figure 5-9. The surface damages caused by

8M nitric acid are shown in Figure 5-10. Discoloration was observed in both 1:2 and 1:5

PLFs. Both PLF surfaces were etched by the acid. The degree of etching was greater in

1:2 PLF than 1:5 PLF. A close up image of 1:2 PLF shows extent of damage caused by

nitric acid. It is clear that the large amount of ligand in the PLF body is causing PLF to be

more prone to damage caused by high concentration nitric acid.

Figure 5-10 Crown ether PLFs damaged by high concentrated nitric acid

5.2.2 Strontium Extraction

The main goal of the study is to separate 90Sr from its daughter 90Y. 90Sr is a pure

beta emitter with a half-life of 28.8 years. It reaches secular equilibrium with its daughter

90Y, another beta emitter, in about 25 days. Simultaneous measurement of both nuclides

is impossible due to a beta energy continuum. It is essential to separate strontium from

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yttrium to accurately quantify the activity of strontium with a beta counter. DtBuCH18C6

is a highly effective extractant for strontium but it has no affinity towards yttrium.

The strontium extraction was approached slightly differently than the plutonium

extraction since it is a beta emitter. PLFs for plutonium extractions were designed to be

used in a semiconductor based alpha spectroscopy, which is not an ideal system to

measure beta energy emitted by strontium. Liquid Scintillation Counter (LSC) is better

suited to measure the strontium decay energies. Due to the different counting system used

in strontium studies, The PLF was prepared in a glass LSC vial instead of a stainless steel

substrate. All other conditions were kept constant including PLF stock solution volume

used in preparing PLF. Figure 5-11 shows diagram of PLF coated LSC vial and actual

picture of the vial. PLFs were air dried for two days to evaporate THF and form a hard

polymer substrate.

Figure 5-11 Crown ether PLF coated LSC vial diagram

A strontium tracer in 3M nitric acid was used in the experiment. The solution was

directly transferred to the vial and equilibrated at three different time periods: 1 hour, 2

hours, and 12 days. LSC vials were agitated during the equilibration time except for the

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12 day sample. Once the prescribed equilibration time was reached, the solution was

removed and the vial was thoroughly rinsed with deionized water. The solution and rinse

water were collected in a clean LSC vial to measure beta activity from the remaining

analytes. 15 mL of LSC cocktail was added to each sample before counting on LSC.

Each sample was counted for 1 hour and background count was subtracted from the

measurement. LSC data shows that DtBuCH18C6 PLF is not capable of extracting

strontium. PLF samples counted with LSC showed no measurable beta activities.

Strontium was not extracted but remained in the nitric acid solution. LSC measurements

from the remaining strontium tracer solution showed that the entire beta activity still

remained in the solution. Polystyrene support structure would be most likely the cause of

ineffectiveness of the ligand in strontium extraction. It is suspected that the polystyrene

chains are preventing the analyte from reaching the ring of the ether groups, which render

DtBuCH18C6 ineffective for strontium extraction.

5.3 2-ethylhexyl 2-ethylhexylphosphonic acid (HEH[EHP])

2-ethylhexyl 2-ethylhexylphosphonic acid (HEH[EHP]) is a phosphoric acid

based extractant, which shows effectiveness in rare earth and other metal elements

separation [72]–[77]. The ligand is developed by Daihachi Chemical Industry Company

Ltd and marketed with the trade name PC-88A. This ligand has similar chemical structure

as HDEHP. The main structure difference between HEH[EHP] and HDEHP is that an

oxygen is missing in one of HEH[EHP]’s hydrocarbon chains as shown in Figure 5-12. A

diluent with low aromatic content is recommended to use with this ligand [77]. The

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ligand has been frequently used as an extractant for lanthanides in solvent extraction [73].

Number of elements were tested and show an affinity to HEH[EHP], including

lanthanides, thorium, and uranium [74], [75]. HEH[EHP] has shown great ability to

effectively separate individual lanthanides with high purity [78].

Figure 5-12 Chemical structure of HEH[EHP]

The ligand was also successfully used in resin bead form for the analyte

extraction. Resin beads were prepared by coating HEH[EHP] onto Amberlite XAD7

beads [73]. A mutual separation of Y-Gd, La-Pr-Nd, and Ho-Er-Tm was successfully

attained with the present resin as the stationary phase and hydrochloric acid as the mobile

phase [73].

A resin bead based extractant is commercially available by Eichrom Industry with

the trade name LN2. The resin bead extraction affinities to elements are shown in Figure

5-13. The anlatye extraction shows dependency on the nitric acid concentration.

Europium and americium uptake by the LN2 resin decreases as well when the pH

increase [72].

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Figure 5-13 HEH[EHP] distribution ratio dependency on HNO3 concentration for various ions

Due to its similar chemical structure to HDEHP, analyte separation behavior of

HEH[EHP] is remarkably similar to the one observed with HDEHP as shown in Figure

5-14. The effectiveness of HEH[EHP] at rare earth extraction was slightly lower than

HDEHP. The extraction efficiency increases nearly linearly as the atomic number

increases.

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Figure 5-14 HEH[EHP] distribution ratio relative to HDEHP [79]

5.3.1 Plutonium Extraction

HEH[EHP] is mainly designed for lanthanide separation; however, due to its

similarity to HDEHP, it has great potential to be also effective for plutonium separation

in PLF form. To test effectiveness of HEH[EHP] for plutonium extraction, 1:5, 1:10, and

1:20 PLFs were tested with 0.01 to 8M nitric acid by the direct stippling method. The

procedure used in this experiment was the same as the one employed in the HDEHP PLF

experiment. Plutonium extraction was most effective with 1:5 PLF in all nitric acid

solutions tested in the experiment. The plutonium recoveries by HEH[EHP] PLFs are

plotted in Figure 5-15. The plutonium percent recoveries by 1:5 PLF are ranging from 17

to 25%. 1:10 and 1:20 PLFs were generally ineffective for plutonium extraction in

conditions tested and plutonium recoveries for both PLFs were similar except for 0.1M.

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The percent recovery for 1:20 PLF was about 10% compared to 5% for 1:10 PLF when

tested with 0.1M nitric acid. This plutonium extraction behavior at 0.1M nitric acid was

noticeable and unexpected. 1:20 PLF has less ligands than 1:10 and it was expect to had

lower amount of active site for analyte extraction. The reasons for such a behavior are

unknown and will need to be further investigated.

Figure 5-15 Plutonium recovery by HEH[EHP] PLF as a function of nitric acid concentration

Tracer solution that was left on PLF after 3 hour equilibration time was collected

and electrodeposited for the analysis. The data gathered from PLF and electrodeposited

samples were used to calculate the unaccounted activity from each sample. Figure 5-16 is

a plot of the computed unaccounted sample activities. The unaccounted activity was

assumed to be deposited below the surface and the activity was contained within the PLF

body. 1:5 PLFs consistently had higher amount of plutonium missing than 1:10 and 1:20

at the same condition. The unaccounted plutonium was higher than 60% for both 0.01

and 0.1M nitric acid solutions. This was the highest missing activity observed from any

0

5

10

15

20

25

30

35

0.01 0.1 1 10

Reco

very

(%)

Nitric Acid (M)

1:5

1:10

1:20

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PLFs tested in entire thesis. This represented that close to 90% of the total plutonium

activity is deposited either on PLF surface or below the surface of 1:5 PLF with 0.01 or

0.1M nitric acid. This represented significant activity recovery, which was close to one

achieved by the conventional electrodeposition method. The limitation of HEH[EHP]

PLF was that even though the entire plutonium extraction percent was high, most of the

activity was contained below the surface. The sample with high internal alpha activity is

not an ideal sample for the silicon based alpha spectroscopy system.

Figure 5-16 Unaccounted plutonium recovery by HEH[EHP] as a function of nitric acid concentration

One noticeable and unexpected behavior of HEH[EHP] PLF was that 1:10 has

lower plutonium recovery than 1:20 PLF. Since 1:5 PLF had the highest total plutonium

recovery, it was expected for 1:10 PLF to perform better in plutonium extraction than the

1:20 PLF due to the higher amount of ligand incorporated into the polymer structure.

Also, since HEH[EHP] is structure analog of HDEHP, extraction behavior was expected

to be similar. In HDEHP PLF studies, plutonium recovery increased as a function of

-20

-10

0

10

20

30

40

50

60

70

80

0.01 0.1 1 10

Reco

very

(%)

Nitric Acid (M)

1:5

1:10

1:20

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ligand mass. The reason for such behavior is not fully understood and will need to be

further investigated.

Due to lower surface plutonium extraction by HEH[EHP] than either HDEHP or

H2DEH[MDP] PLFs, there was no merit in using HEH[EHP] for plutonium extraction at

this point. No further studies were carried out for this ligand. The overall performance

this ligand may be improved by concentrating ligands on the surface of the PLF.

However, it is out of the scope of this thesis.

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6. Chapter 6

Environmental Sample Analysis

PLFs were developed as a field deployable technique. It is important to test PLF

in relevant environments with appropriate samples to fully understand the capabilities

and limitations of the extractant system. H2DEH[MDP] PLF was exclusively used in this

chapter. Environmental samples were divided into two categories: liquid and solid.

Different types of samples require distinctive sample preparation procedure. Solid

samples are generally harder to process compared to liquid samples. Solid samples first

need to be completely dissolved into a solution to measure complete content of alpha or

beta analytes. Complete dissolution of a sample is generally time consuming and a

complicated procedure. Another approach is to leach out analyte of interest from the solid

matrixes. This method may not completely extract analytes from the solid matrixes but it

would offer simpler approach than the complete dissolution method. Leaching is ideal for

preparing samples for isotopic measurements where the entire analyte content is not

needed to perform a reliable analysis. The field deployable procedures were established

for water and soil samples. Two soil samples were examined: National Institute of

Standards and Technology (NIST) Rocky Flats soil Standard Reference Material (SRM)

and Mortandad Canyon soil in Los Alamos. Water samples were also collected from

Mortandad Canyon.

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6.1 Soil Sample Analysis

Leaching and fusion procedures were established for the soil samples. The

procedures were kept simple as possible to be able to perform out in the field. Field

deployable methods would have great limits on reagents that can be transferred and used

due to the regulations and limitations in a deployed facility.

6.1.1 Soil Characterization

The environmental soil samples were collected from the creek bed in Mortandad

Canyon. The soil samples were characterized before the leaching or fusion studies due to

the lack of any prior knowledge on the sample. The soil samples were first analyzed with

a high purity germanium (HPGe) detector system. Gamma spectroscopy is a non-

destructive technique and requires little sample preparation before the analysis. Soil was

dried in a muffle furnace for 48 hours. Dried soil was placed in four circular containers

(pucks) as shown in Figure 6-1 and analyzed with HPGe detectors.

Figure 6-1 Mortandad Canyon soil samples

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About 33g of soil was contained in each puck and gamma spectroscopy shows similar

spectra for all four samples. The spectra are attached in Appendix D and activities from

radionuclide measured with HPGe are given in Table 6-1. The highest activity was from

228Ac, which has half-life of 6.15 hours and decay to 228Th.

Table 6-1 Mortandad Canyon soil radionuclide activities measured with HPGe Radionuclide Activity (dpm/g)

137Cs 11.880±1.022 212Pb 32.574±1.882 226Ra 1.544±0.087 228Ac 204.946±15.412 235U 0.369±0.030

241Am 3.303±0.169

Elemental composition of Mortandad Canyon soil was further analyzed with the

neutron activation analysis (NAA). The analysis was performed at the Radiation Science

& Engineering Center at Penn State University. Two sets of 500 mg of Mortandad

Canyon soil were irradiated for 2 hours at a power level of 200 kW. The flux was

approximately 2x1012 n/cm2-s at the irradiation position. The comparative analysis was

performed by irradiating two NIST certified standard reference materials simultaneously

with the sample. The reference materials used were SRM278 - Obsidian Rock and

SRM679 - Brick Clay. Samples and SRMs were analyzed with HPGe detector system

after decay time of 6, 10, 17, and 23 days. The result of NAA elemental analysis is shown

in Table 6-2.

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Table 6-2 Elemental information gained from NAA

Element Concentration Sodium 3.37 ± 0.18 wt% Potassium 3.969 ± 0.264 wt% Chromium 4.63 ± 1.53 ppm Hafnium 4.2 ± 0.3 ppm Barium 244.9 ± 65.0 ppm Scandium 1.23 ± 0.08 ppm Rubidium 81.3 ± 9.7 ppm Iron 0.95 ± 0.05 wt% Ytterbium 2.33 ± 0.12 ppm Tantalum 1.0 ± 0.3 ppm Cobalt 1.30 ± 0.33 ppm

A fusion digestion was performed on the environmental soil samples to measure

plutonium activity from the soil. 1g of soil was placed in a zirconium crucible with 10g

of sodium hydroxide. Samples were then melted using a muffle furnace at high

temperature. Soil samples processed with the muffle furnace are shown in Figure 6-2.

Once soil was fused, sample was removed from the crucible using DI water. The samples

were then filtered on a 0.8 μm pore size filter paper. Filtered analytes were then

redissolved by running 8M nitric acid through the filter. Column chromatography was

performed to isolate plutonium from other analytes before electrodepositing onto

stainless steel substrate. 12 ml of Bio-Rad AG 1x4 resin was used in the cleanup and

plutonium was eluted with 1.2M HCl-H2O2. 1.761 dpm/g and 6.088x10-1 dpm/g were

measured using a fusion procedure for 239+240Pu and 238Pu, respectively.

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Figure 6-2 Fusion sample (A) before (B) after processing with the muffle furnace

The great advantage of fusion over other sample preparation techniques is that the

entire sample is digested, dissolved and analyzed. However, the fusion process is

complex and time consuming. Since the entire sample was dissolved, an extensive sample

cleanup was requried to process the sample. The fusion in conjunction with the classical

sample preparation chemical process took few days from start of dissilution of the sample

until the alpha analysis was complete.

6.1.2 Mortandad Canyon Soil Leaching Study

The analyte leaching process will offer more ideal solution to processing samples

out in the field. The main focuses in developing this process were to minimize use of

reagents and simplifying the procedure. The Mortandad Canyon soil and Rocky Flats

standard soil were used to establish the leaching procedure. The canyon soil samples

were used as is without any processing, including homogenization. The sample variation

would be higher without the homogenization, but the process is time consuming and may

be inadequate to perform in the field. The analyte leaching was performed using white

distilled vinegar and nitric acid. Vinegar is easy to purchase and there is no regulation

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limiting transferring of material, which make it a good candidate for field use. However,

vinegar is a weak acid and the distilled vinegar is only 5% acetic acid. Nitric acid is more

favorable for the leach operation but transportation is regulated by U.S Department of

Transportation [80]. In this experiment, white distilled vinegar and concentration of nitric

acids ranging from 0.1 to 16M were tested to leach analytes from the soil. Roughly 10g

of soil and 20g of reagent were used per each sample. Samples were vortexed for

approximately a minute to suspend particles in solution then left to settle down for 24

hours. Samples were centrifuged to separate soil from solution then filtered with 0.02 μm

pore size syringe filter. Filtering process removed fine particles from the reagent and

difference made by filtering can be seen in Figure 6-3.

Figure 6-3 Leached solution (A) before (B) after syringe filtering

The aliquot of leached solutions were first analyzed with ICP-MS to gain

elemental information. Rest of samples were processed and counted with alpha

spectroscopy to measure activity. Nitric acid was able to extract many elements from the

soil. The elemental information is given in Table 6-3. The mass spectroscopy

measurement showed that the iron was the most abundant element in the leached

solution. The iron content was still low to be visibly observed from the leach solution.

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Table 6-3 Elements leached from Mortandad Canyon soil using nitric acid

1M nitric acid 8M nitric acid 16M nitric acid Arsenic (ng/mL) 7.79±1.29 15.50±1.70 15.22±0.89 Yttrium (ng/mL) 243.40±17.95 243.47±11.25 283.28±10.86

Zirconium (ng/mL) 9.93±2.75 74.58±5.04 110.98±6.15 Niobium (ng/mL) 2.32±0.45 4.85±0.65 1.86±0.37

Molybdenum (ng/mL) 1.80±1.17 5.71±1.45 6.19±1.44 Cadmium (ng/mL) 1.54±0.57 1.50±0.45 2.21±0.44

Tin (ng/mL) 3.25±0.81 3.57±0.67 2.67±0.71 Barium (ng/mL) 799.33±67.20 700.04±42.72 686.72±40.37

Lanthanum (ng/mL) 530.70±35.50 485.22±19.14 517.50±19.67 Cerium (ng/mL) 656.14±39.06 982.87±40.84 793.06±30.09

Praseodymium (ng/mL) 139.41±8.46 128.15±5.10 135.67±5.84 Neodymium (ng/mL) 503.75±31.07 461.34±19.34 492.89±21.16 Samarium (ng/mL) 93.31±5.79 85.36±4.33 92.84±4.32 Europium (ng/mL) 4.24±0.30 3.84±0.23 4.86±0.22

Gadolinium (ng/mL) 109.41±7.47 103.85±5.54 113.34±6.05 Terbium (ng/mL) 11.07±0.72 10.52±0.47 11.46±0.49

Dysprosium (ng/mL) 50.54±3.20 49.19±1.94 54.19±2.09 Holmium (ng/mL) 9.65±0.60 9.39±0.40 10.50±0.48 Erbium (ng/mL) 26.15±1.92 25.66±1.54 28.90±1.76 Thulium (ng/mL) 3.13±0.28 3.16±0.18 3.43±0.19

Ytterbium (ng/mL) 21.34±1.58 21.36±1.04 23.40±1.24 Lutetium (ng/mL) 2.84±0.17 3.01±0.22 3.27±0.18 Hafnium (ng/mL) 0.83±0.28 2.98±0.35 4.39±0.60

Lead (ng/mL) 543.81±36.52 207.17±11.69 211.50±11.41 Thorium (ng/mL) 44.19±4.21 54.31±4.31 64.17±4.23 Uranium (ng/mL) 6.49±0.79 6.51±0.65 6.72±0.59 Rubidium (ng/mL) 7.20±1.15 22.44±2.30 17.87±1.70 Strontium (ng/mL) 101.58±26.09 68.31±17.78 85.89±16.69 Sodium (ng/mL) 2278.91±1252.26 2489.30±1029.05 1801.09±1287.47

Magnesium (ng/mL) 2903.35±486.19 2770.15±721.12 2319.07±526.21 Potassium (ng/mL) 4303.74±343.62 4704.81±282.30 4778.59±244.43 Titanium (ng/mL) 141.90±78.30 310.91±128.06 11.88±59.19

Vanadium (ng/mL) 23.12±31.34 48.98±29.10 27.25±23.08 Chromium (ng/mL) 95.18±12.77 23.47±12.50 26.34±8.00 Manganese (ng/mL) 3347.92±235.78 3967.06±222.38 4585.73±206.77

Iron (ng/mL) 25568.97±2776.14 40229.32±2809.24 30530.60±3007.38 Cobalt (ng/mL) 14.91±4.31 17.31±2.49 18.10±2.03 Nickel (ng/mL) 51.35±43.69 29.20±43.06 39.72±34.73 Zinc (ng/mL) 860.71±139.41 688.31±157.56 730.88±337.02

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The soil samples from Mortandad Canyon soil had about 1% (wt) of iron, and only

5.11x10-3% of iron from soil was leached using 1M nitric acid. The leached solutions

were processed with the classical column chromatography and electrodeposition to

measure plutonium activity in the leach solutions. The plutonium leaching capacities

increased with the nitric acid concentration. 239+240Pu and 238Pu activities leached with

nitric acids are plotted in Figure 6-4. 1 to 16M nitric acids were all effective in leaching

plutonium out of the soil. The highest plutonium recoveries were achieved with 16M

nitric acid. Since lower nitric acid is easier to handle and process, 1M nitric acid was

further studied for analyte extraction in the time dependency experiment.

Figure 6-4 Plutonium leaching dependency on the nitric acid concentration

The leaching dependency on time was tested from 1 to 24 hours. All samples

from the time study showed measurable plutonium activities. 239+240Pu leached activities

are plotted in Figure 6-5 and it shows a logarithmic trend. The 24 hour leaching extracted

about 0.38 dpm/g, which was four times lower than one achieved from the previous

0

0.5

1

1.5

2

2.5

0.01 0.1 1 10 100

Pu A

ctiv

ity p

er g

ram

of s

oil (

dpm

/g)

Nitric Concentration (M)

239+240Pu

238Pu

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study. The procedure was identical between two studies. Most likely the cause of the

discrepancy is due to unhomogenized soil. Soil was collected in the same location on the

same date but there were still possible variations from sample to sample. White distilled

vinegar was generally ineffective in leaching plutonium from the soil sample. The leach

capacity of the vinegar reached maximum around 2 hours then slightly decrease

thereafter.

Figure 6-5 Plutonium leaching dependency on time for 1M ntiric acid and white distilled vinegar

Mortandad Canyon leached samples were further processed with 1:20

H2DEH[MDP] PLF. In this study, leaching time and exposure time were varied to find

the most optimal time to process soil sample with PLF. Analytes were leached out from

soil by placing samples in 1M nitric acid for 1, 2, 3, or 24 hours. Nitric acid solution was

removed then syringe filtered after the prescribed leaching time. 3 mL of leached solution

was directly stippled onto PLF then removed after prescribed exposure time. The

0

0.05

0.1

0.15

0.2

0.25

0.3

0.35

0.4

0.45

0 5 10 15 20 25 30

239 P

u Ac

tivity

per

gra

m o

f soi

l (dp

m/g

)

Time (hr)

1M nitric

Vinegar

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exposure times were also varied from 1 to 3 hours. Overall 239Pu activities were low for

the entire samples prepared with Mortandad Canyon soil as shown in Figure 6-6. Even

with the low plutonium recovery, plutonium peaks were easily distinguishable above the

background with 24 hour counts. PLF samples prepared with 24 hour leaching solution

had noticeably higher plutonium activities than the rest of the samples. The highest

239+240Pu activity of 0.315 dpm was seen with 24 hour leaching and 3 hour exposure. Soil

leaching time between 1 and 3 hours showed no difference in plutonium extracted onto

PLF surface.

Figure 6-6 239+240Pu extracted with 1:20 H2DEH[MDP] PLF at different leaching and exposure time

6.1.3 Rock Flats Soil Leaching Study

The leaching study was also performed with Rocky Flats soil. The leaching

procedure was the same as the one used with Mortandad Canyon soil. The Rocky Flats

soil is a NIST standard reference material, which was collected from Rocky Flats Plant in

Colorado. The soil was homogenized with an air jet mill to an average particle diameter

0.0E+00

5.0E-02

1.0E-01

1.5E-01

2.0E-01

2.5E-01

0 1 2 3 4

239+

240 P

u ac

tivity

(dpm

)

Exposure time (hrs)

1 hr

2 hrs

3 hrs

24 hrs

Leaching time

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of 8 μm and more than 99% of the particles were less than 20 μm in diameter [81]. The

soil is a certified standard and information is given in Table 6-4. 240/239Pu ratio is not

certified and only uncertified value is listed on the material certification.

Table 6-4 Rocky Flats standard soil certified radionuclide activities Radionuclide Activity (mBq/g)

238Pu 0.278±0.041 239+240Pu 16.8±1.8

238U 39.6±3.0 234U 40.4±3.0 235U 1.88±0.53 90Sr 10.5±1.3

Vinegar and nitric acids were used as the leaching reagents. The Rocky Flat standard soil

was noticeably finer than the Mortandad Canyon soil. Roughly 10g of soil was

transferred to a centrifuge tube and 20g of reagent was added to the soil. Samples were

vortexed for approximately a minute to suspend particles in the solution then left to settle

for 24 hours. Particle sizes were small and portion of soil floated on the nitric acid.

Samples were centrifuged to separate soil from nitric acid solution. Once the soil had

settled, solutions were removed and filtered with a syringe filter to remove any particles

larger than 0.02 μm. Solution colors differ vastly based on the acidity as shown in Figure

6-7 and Figure 6-8. The darker color indicated that iron was also extracted from the soil.

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Figure 6-7 Rocky Flats soil leaching with vinegar or various concentration nitric acid solutions

Samples were traced with 242Pu and cleaned using column chromatography before

electrodeposition. Alpha spectroscopy showed that 8 and 16M nitric acids were able to

leach plutonium out of the soil matrix. 40% and 82% of 239+240Pu activity was extracted

from the Rocky Flat soil with 8M and con nitric acid, respectively. 239+240Pu activity

removed by vinegar and nitric acids are shown in Table 6-5. 238Pu content in the soil

sample was too small to be effectively leached and measured with alpha spectroscopy.

Figure 6-8 Rocky Flats soil leached solutions after syringe filtering

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Table 6-5 239+240Pu leached activities from Rock Flats soil and percent activity recoveries based on certified values

Leaching reagent 239+240Pu activity (dpm/g) Percent 239+240Pu leached (%)

Vinegar (2.758±1.625)x10-3 0.27±0.16 0.1M nitric acid (1.942±1.942)x10-3 0.19±0.19 1M nitric acid (2.118±0.397)x10-2 2.10±0.45 8M nitric acid (3.969±0.305)x10-1 39.37±5.19 16M nitric acid (8.248±0.359)x10-1 81.82±9.46

The Rocky Flats soil was further analyzed with 1:20 H2DEH[MDP] PLF. Based

on the leaching information, analytes were leached from the soil using 8 and 16M nitric

acids. Most leached samples were centrifuged then filtered with 0.02 μm pore size

syringe filter to remove any particles. One sample was processed without centrifuging to

check the possibility of skipping the step. A centrifuge may not be available out in the

field and it will be beneficial to possibly eliminate the step. The sample was processed

with a combination of filter paper and syringe filter. Without centrifuging the sample,

there was no clear separation between liquid and soil. Filtering took a long time and

became a cumbersome process due to the large amount of finely grounded soil that was

suspended in a solution. The filter paper was quickly clogged up by the soil and had to be

consistently replaced to effectively filter the soil. All samples were traced with 242Pu then

dried on a hot plate. A large amount of brownish residue was left in the beakers as shown

in Figure 6-9. The uncentrifuged sample had slightly darker color than the centrifuged

samples. The residues were redissolved by adding 3mL of 0.1M nitric acid. The nitric

acid was then stippled onto a PLF. The difference in the solution color between

centrifuged and uncentrifuged samples was clearly shown after stippling as shown in

Figure 6-10. Stippled solutions were removed after 3 hour exposure. PLFs were

thoroughly rinsed with DI water and showed no discoloration after the exposure.

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Figure 6-9 Residue left on beaker after leached nitric acid was dried

Figure 6-10 Rocky Flats leached solution stippled on 1:20 H2DEH[MDP] PLFs

All samples were analyzed with alpha spectroscopy to measure plutonium. No activity

above the background level was measured for all samples. Even 242Pu tracer was not

extracted by PLF. It is a good indication that high concentration of iron was precipitating

plutonium out of solution, which rendered PLF inactive for the analyte extraction. The

elemental composition of the Rocky Flats SRM soil is shown in Table 6-6 [81]. The

elemental composition was measured using X-ray fluorescence (XRF). Relatively large

concentration of iron was presented in the soil and nitric acid was also leaching large

quantity of iron from the soil matrix. The current leaching procedure is inadequate for

soil with large iron content. The procedure had to be modified to remove iron from

solution for PLF to be effective in plutonium extraction. One way to eliminate iron is to

use hydrogen peroxide to convert Fe(II) in Fe(III) then filter iron precipitates from the

solution.

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Table 6-6 Elemental composition of Rocky Flats SRM Element Mass percent (%) Element Mass percent (%) Silicon 36 Chlorine 0.004 Aluminum 4.5 Chromium 0.033 Iron 2.6 Copper 0.003 Magnesium 0.29 Gallium < 0.001 Calcium 0.40 Nickel 0.018 Sodium 0.65 Lead 0.003 Potassium 1.7 Rubidium 0.007 Titanium 0.20 Strontium 0.011 Phosphorus 0.07 Vanadium 0.004 Manganese 0.054 Yttrium 0.002 Carbon 1.5 Zinc 0.007 Sulfur 0.02 Zirconium 0.02

6.2 Water Sample Analysis

Water samples were also collected from Mortandad Canyon and used to establish

PLF procedures. Water samples were simpler to process than solid samples. Analytes

were already in solution and the procedure could be simplified compared to solid

samples. Two approaches were taken to prepare environmental water samples. The first

approach was to directly stipple solution on PLF without any chemical processing. The

second approach is to acidify water with nitric acid before processing with PLF.

6.2.1 Environmental Water Characterization

Mortandad Canyon water was first analyzed for plutonium and uranium contents.

500mL of water was traced with 242Pu and cleaned up using column chromatography. 12

ml of Bio-Rad AG 1x4 resin was used in the cleanup and plutonium was eluted with

1.2M HCl-H2O2.

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Plutonium activities were low for the Mortandad Canyon water. 4.35x10-3 dpm/ml

of 239+240Pu and 9.38x10-4 dpm/ml of 238Pu were measured with electrodeposited samples.

The activities may be too low to effectively analyze with the PLF method. Only about

3mL solution can be stippled onto a standard PLF and that translates to 1.31x10-2 and

2.81x10-3 dpm for 239+240Pu and 238Pu, respectively for each sample. Typical sample

activities will be a lot lower considering the efficiency of the PLF system.

6.2.2 Environmental Water Processing with PLF

The pH of the solution is a critical parameter in the extraction of plutonium from

solution with H2DEH[MDP] PLF. Previous studies showed that H2DEH[MDP] PLF

performed well between 0.01 to 1M nitric acids. PLF analyte extraction capability at

natural pH was not examined in previous experiments. In this section, PLFs were tested

with environmental samples to examine the effectiveness of H2DEH[MDP] PLF in

natural pH. Also, PLFs were carefully examined for any physical degradation caused by

the environmental samples.

The procedure was kept as simple as possible. The environmental sample was

only cleaned with a syringe filter then directly stippled onto PLF for three hours. The

water was relatively clean and only a minimum amount of particulates were visible. The

procedure was simple and easy to perform in any setting. However, alpha spectroscopy

measurements showed no detectable plutonium activities. This is most likely due to the

low activities in the water samples. Also, the non-detectable activity could be due to

ineffectiveness of PLF in natural pH solution. Mortandad Canyon water had relatively

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low plutonium content for the experiment, but it was the only contaminated

environmental water sample available for the PLF experiment. It was decided to prepare

a simulated water sample to best emulate a higher activity environmental sample. 242Pu

was first dried in a beaker, then filtered Mortandad Canyon sample was added to re-

dissolve plutonium. The simulated water was tested with the stippling method. The 242Pu

recovery by 1:20 H2DEH[MDP] PLFs were low at about 2.5% as shown in Table 6-7.

However, activity was detectable with the silicon alpha spectroscopy system and it was

well above the background. This experiment clearly demonstrated that PLF is capable of

extracting plutonium from environmental sample at natural pH. The procedure was

simple and did not require any addition of chemical reagents, which made it more

suitable field sample preparation than the conventional technique.

Table 6-7 Simulated environmental water sample plutonium recoveries Sample Type Pu Recovery (%) Natural pH 2.45±0.34 Acidified 41.32±5.95

H2DEH[MDP] PLF has performed well between 0.01 to 1M nitric acids in

previous experiments. Mortandad Canyon water had pH of 6. To put the water sample in

more favorable condition for analyte extraction, nitric acid was added to acidify the

filtered sample. The solution was then stippled on PLFs for three hours to extract

plutonium. No detectable plutonium was extracted from Mortandad Canyon water by

PLF. Since low pH was more favorable for plutonium extraction by H2DEH[MDP], the

low recovery was most likely due to the low plutonium content in the water samples. The

experiment was repeated with the simulated environmental water and showed

considerably higher plutonium recovery than non-acidified water. 41% of 242Pu was

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recovered, which was about 17 times higher recovery than one seen from the non-

acidified sample.

6.3 Environmental Sample Analysis Conclusions

Procedures were established to process environmental samples with

H2DEH[MDP] PLF. The fusion digestion was performed using sodium hydroxide with

zirconium crucible. The method dissolved the entire sample and an extensive sample

cleanup was required to process the sample. The plutonium analysis using fusion method

took a few days from start of the fusion to the alpha counting. The leaching procedure

was developed to shorten and simplify the soil sample processing with PLF. Nitric acid

was able to leach plutonium out of Mortandad Canyon and Rocky Flats soils. However,

only plutonium leached out from Mortandad Canyon was extracted from the solution

using PLF. Overall 239Pu activities were low for the entire samples prepared with

Mortandad Canyon soil. 0.315 dpm of 239+240Pu was the highest activity measured using

PLF system. Even with the low plutonium recovery, plutonium peaks were

distinguishable above the background with 24 hour counts. The ICP-MS measurement

done on the Mortandad Canyon leached solution showed that nitric acid was able to leach

many elements along with plutonium. Out of elements measured with the mass

spectroscopy, iron was the most abundant element in the leached solution. The soil

samples from Mortandad Canyon soil had about 1% (wt) of iron and 5.11x10-3% of iron

from soil was leached using 1M nitric acid.

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Rocky Flats soil was not effectively processed with PLF. Plutonium was not

extracted by PLF from the Rocky Flats leached solution. Rocky Flats samples contained

2.6% (wt) of iron and it leached together with plutonium. The leached solutions from the

Rocky Flats soil had dark reddish color. High concentration of iron interfered and

prevented plutonium from being extracted from solution by PLF. Even 242Pu tracer added

to the sample was not extracted by PLF. The leaching procedure would need to be

modified to process soil samples with high iron concentration.

Water samples were simpler to process with PLF than soil samples.

Approximately 2.5% of plutonium was extracted with 1:20 H2DEH[MDP] PLF by

directly stippling water onto PLF. The plutonium extraction was greatly increased by

acidifying the environmental water with nitric acid then stippled onto PLF. About 41% of

plutonium was recovered after acidifying the sample. Acidification of natural pH sample

is preferable due to higher plutonium recovery it provided compared to non-acidified

samples. However, if initial sample activity is high enough, environmental water can

directly be processed with PLF without adding any reagent to a sample.

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Chapter 7

Summary and Conclusions

The goal of this research was to develop a novel method to selectively and rapidly

extract uranium, plutonium, and strontium from solutions using Polymer Ligand Film

(PLF). PLF was synthesized and tested for their ability to absorb radionuclides directly

from solutions and produce sources of sufficient quality for radiometric techniques. High

sample throughput is critical in an emergency response since there is a potential for

enormous number of samples. Current radioanalytical techniques are not well suited for

rapid analysis or pre-screening large numbers of samples to decide which to move onto a

more accurate but time consuming set of analyses. Conventional alpha spectrometry

techniques take a couple days to a week to complete depending on the sample. The newly

developed PLF method greatly shortens and simplifies the analyte extraction and sample

preparation for radiometric analysis. Samples can be analyzed within one to two days

using the PLF system.

Five different ligands were tested for the analyte extraction: bis(2-ethylhexyl)

methanediphosphonic acid (H2DEH[MDP]), di(2-ethyl hexyl) phosphoric acid (HDEHP),

trialkyl methylammonium chloride (Aliquat-336), 4,4'(5')-di-t-butylcyclohexano 18-

crown-6 (DtBuCH18C6), and 2-ethylhexyl 2-ethylhexylphosphonic acid (HEH[EHP]).

H2DEH[MDP] and HDEHP which showed effectiveness for plutonium extraction were

extensively studied. The extraction of strontium was exclusively studied with

DtBuCH18C6. In PLF form, DtBuCH18C6 became completely ineffective for strontium

extraction.

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H2DEH[MDP] PLFs were effective in plutonium and uranium extraction.

H2DEH[MDP] performed best with 1:10, 1:15, and 1:20 ratio PLFs for the plutonium

extraction. 50.44% and 47.61% of plutonium were extracted on the surface of PLFs with

1M nitric acid for 1:10 and 1:20 PLF, respectively. H2DEH[MDP] PLF was also capable

of co-extracting or selectively extracting plutonium over uranium depending on the PLF

composition. With 1:5 PLF, 23% of plutonium and 20% uranium were simultaneously

extracted with 1M nitric acid. Unlike 1:5, both 1:10 and 1:20 PLFs were extracting

plutonium preferably over uranium under the same conditions. H2DEH[MDP] PLF

showed extraction consistency similar to the electrodeposited samples. The overall

analyte recovery was lower than electrodeposited samples. The typical electrodeposited

samples have analyte recovery of over 80%.

HDEHP PLFs were effective in plutonium extraction. 1:5 PLF showed best

combination of plutonium extraction and alpha spectrum resolution from the eight

different PLF compositions tested. The percent plutonium recovery was 49%, which was

higher than any other HDEHP PLFs except for 1:2 PLF. The main deficiency from 1:2

PLF is that the sample attenuation degraded the resolution of the alpha spectrum. 1:5 PLF

spectra had a tailing term of 18.65 based on the Bortels’ alpha peak fitting equation.

However, 1:2 PLFs showed 305.19 for the tailing. The spectra from 1:2 HDEHP PLFs

were unusable in any meaningful analysis due to the large tailing.

HDEHP PLF was surprisingly ineffective for uranium extraction from nitric acid.

The PLFs tested with natural uranium tracer showed no significant uranium recovery in

the entire conditions tested. The ligand itself is actually effective for both plutonium and

uranium in liquid/liquid and resin bead based extraction. The polystyrene structure is

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causing ligand to behave differently than in other matrixes. One of the main deficiencies

of 1:5 HDEHP PLFs was inconsistency in plutonium recovery shown from different PLF

batches: one had three times higher plutonium recovery than the other.

Both H2DEH[MDP] and HDEHP PLFs were consistently susceptible to

plutonium penetrating and depositing below the surface. The internal radiation within the

body of PLF did not cause any spectra degradation. The analyte penetration issue was

beneficial in the TIMS analysis because the extra plutonium contained in PLF body gave

additional signal in the analysis. Plutonium was successfully back-extracted from PLFs

then processed for TIMS to measure plutonium isotopics. TIMS analysis was completed

without any issues and isotopic measurement was accurate.

Environmental samples were effectively processed with 1:20 H2DEH[MDP] PLF.

The extraction system was very effective in extracting plutonium from environmental

water samples with minimal sample processing. About 41% of plutonium was recovered

by first acidifying the water sample with nitric acid then stippling onto PLF. Soil samples

were more difficult to process with PLF. Analytes were first removed from the soil

matrices before being processed with PLF. Nitric acid was able to leach plutonium out of

soil samples along with other elements. The performance of PLF was highly dependent

on the composition of the soil. Samples with low iron content were processed with the

PLF system, and plutonium activities were measured with alpha spectroscopy. However,

processing samples with large iron concentrations were unsuccessful with the current

procedure. Also, the plutonium recovery was 30 to 40% lower with PLF compared to the

classical chemical procedure. Even with such limitations, the PLF technique simplified

the procedure and offered considerably reduced sample analysis time.

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The PLF method is a great screening tool to deploy to decrease the number of

samples required for more extensive analysis. The entire sample preparation to analysis

was done within one to two days. The classical method for alpha samples takes two days

to a week in comparison. The technique also requires minimal chemicals, and it is field

deployable. The reduction in time and simplified procedure make this technique ideal for

the post-detonation emergency response.

7.1 Recommendations and Future Studies

It is important to further investigate the PLF extractant system with other relevant

sample types. During the incident response, various different types of samples will need

to be analyzed. As shown in soil analysis, the current leaching procedure is not adequate

to process all types of samples. Soil samples with large amounts of iron cannot be

processed with PLF. The interference introduced by iron is not unique to PLF, but it is a

well-known issue even for the classical sample preparation methods. The classical

chemical method uses column chromatography to separate plutonium from the rest of

analytes. The column chromatography for plutonium separation is well-established but

cumbersome and difficult to perform out in the field. Further investigation will be

performed to find simple process to remove iron from the leach solution. Another type of

sample that may be available at the incident location is fused nuclear explosion debris.

These samples are more complicated to process and nitric acid leaching will probably be

ineffective in removing plutonium from the matrix. The future studies will investigate the

possibility of using other chemicals to leach plutonium from fused debris samples. The

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fusion digestion technique used to characterize the Mortandad Canyon Soil is also

capable of processing the refractory debris. The entire sample will be digested with this

technique and there might be elements that may cause the interference with analyte of

interest. A simple clean up procedure will be needed to remove these interferences

conjunction with the fusion technique.

All of the PLF preparation methods used in this study relied on the solvent to

dissolve the ligand and polystyrene. The solvent, THF, had a tendency to encapsulate in

the PLF medium and cause HDEHP PLFs to have inconsistency in plutonium extraction.

A further study is planned to modify PLF preparation method to be solventless. The

solventless PLF preparation method may make the PLF more consistent in the analyte

extraction and also eliminate the creation of bubbles in the PLF body.

Also, more experiments will be needed to shorten the total time needed for the

TIMS analysis for PLF samples. With the current method, the entire process takes least 3

to 4 days to complete. One way to decrease the time will be using a direct technique for

mounting plutonium onto TIMS filaments. Preliminary studies showed that direct

mounting has great potential to be utilized in TIMS analysis. It will decrease the analysis

time considerably and may even provide enhancement in the signal. Further studies are

required to fine tune the method to be effective.

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Appendix A

Counting Software Code

The counting software was developed in C++ language in Microsoft Windows® environment. The plutonium locations from the digital autoradiography image were inputted into the software. The location information is divided into rectangular sections and plutonium distribution was analyzed.

#include <iostream> #include <fstream> #include <cmath> #include <iomanip> using namespace std;

int main() {

int mat[100000][2]; //Track locaton matrix double count[21][21]; //Counter for tracks in each section double x_range[21], y_range[21]; //Store section start & end of section int x_min, x_max, y_min, y_max; double x_sec, y_sec, total=0.0; int x_col; //Location matrix colume size double x_sub, y_sub; //Section size ifstream InFile("data.txt"); //input data from data.txt file ofstream OutFile("Track_data.cvs"); cout<<"Track Counting Software"<<endl; cout<<"------------------INPUT--------------------"<<endl; cout<<"How many sections in X: "; cin>>x_sec; cout<<endl<<"How many sections in Y: "; cin>>y_sec; InFile>>x_col; //Input colume size //Input track location for(int i=0; i<x_col; i++) { for(int j=0; j<2; j++) { InFile>>mat[i][j]; } } //Find min and max x_min=x_max=mat[0][0];

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y_min=y_max=mat[0][1]; for(int i=0; i<x_col; i++) { if(mat[i][0]<x_min) x_min=mat[i][0]; else if(mat[i][0]>x_max) x_max=mat[i][0]; } for(int i=0; i<x_col; i++) { if(mat[i][1]<y_min) y_min=mat[i][1]; else if(mat[i][1]>y_max) y_max=mat[i][1]; } //Calculate section size x_sub=(x_max-x_min)/x_sec; y_sub=(y_max-y_min)/y_sec; //Store range info in an array x_range[0]=x_min; y_range[0]=y_min; OutFile<<"X range"<<endl; OutFile<<x_range[0]<<"\t"; for(int i=1; i<=x_sec; i++) { x_range[i]=x_range[i-1]+x_sub; OutFile<<x_range[i]<<"\t"; } OutFile<<endl<<"Y range"<<endl; OutFile<<y_range[0]<<"\t"; for(int i=1; i<=y_sec; i++) { y_range[i]=y_range[i-1]+y_sub; OutFile<<y_range[i]<<"\t"; } OutFile<<endl<<endl; //Counting tracks in each section. cout<<endl<<"------------------RESULT--------------------"<<endl; cout<<"Track counts per section:"<<endl; OutFile<<"Track counts per section:"<<endl; for(int i=0; i<y_sec; i++) { for(int j=0; j<x_sec; j++) { count[i][j]=0;

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for(int k=0; k<x_col; k++) { if(mat[k][0]>=x_range[j] && mat[k][0]<x_range[j+1] &&

mat[k][1]>=y_range[i] && mat[k][1]<y_range[i+1]) count[i][j]++; else if (mat[k][1]==y_max) { if (mat[k][1]<=y_range[i+1] &&

mat[k][0]>=x_range[j] && mat[k][0]<x_range[j+1]) count[i][j]++; } else if (mat[k][0]==x_max) { if (mat[k][0]<=x_range[j+1] &&

mat[k][1]>=y_range[i] && mat[k][1]<y_range[i+1]) count[i][j]++; } else if(mat[k][0]>=x_range[j] && mat[k][0]==x_max &&

mat[k][1]>=y_range[i] && mat[k][1]==y_max) count[i][j]++; } cout<<count[i][j]<<"\t"; OutFile<<count[i][j]<<"\t"; } cout<<endl; OutFile<<endl; } cout<<endl; //Total track in sample for(int i=0; i<y_sec; i++) { for(int j=0; j<x_sec; j++) total=total+count[i][j]; } //Checking count data if (total==x_col) { cout<<endl<<"Total number of tracks in sample: "<<total<<endl; OutFile<<endl<<"Total number of tracks in sample: "<<total<<endl; cout.precision(2); cout<<endl<<"Area per section (pixel^2):

"<<double(x_sub*y_sub)<<endl; OutFile<<endl<<"Area per section (pixel^2):

"<<double(x_sub*y_sub)<<endl; }

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//Calculating count uncertainty cout<<endl<<"Counting uncertainty per section: "<<endl; OutFile<<endl<<"Counting uncertainty per section: "<<endl; for(int i=0; i<y_sec; i++) { for(int j=0; j<x_sec; j++) { cout.precision(2); cout<<fixed<<double(sqrt(count[i][j]))<<"\t"; OutFile<<fixed<<double(sqrt(count[i][j]))<<"\t"; } cout<<endl; OutFile<<endl; } //Calculating percent distribution cout<<endl<<"Percent distribution of tracks per section: "<<endl; OutFile<<endl<<"Percent distribution of tracks per section: "<<endl; for(int i=0; i<y_sec; i++) { for(int j=0; j<x_sec; j++) { cout.precision(2); cout<<fixed<<double(count[i][j]/total*100.0)<<"%\t"; OutFile<<fixed<<double(count[i][j]/total*100.0)<<"%\t"; } cout<<endl; OutFile<<endl; } //Calculating track density cout<<endl<<"Track density per section (track/pixel^2): "<<endl; OutFile<<endl<<"Track density per section (track/pixel^2): "<<endl; for(int i=0; i<y_sec; i++) { for(int j=0; j<x_sec; j++) { cout<<scientific<<double(count[i][j]/(x_sub*y_sub))<<"\t"; OutFile<<scientific<<double(count[i][j]/(x_sub*y_sub))<<"\t"; } cout<<endl; OutFile<<endl; } cout<<endl<<"**Result is saved in Track_data.cvs file**"<<endl<<endl; return 0; }

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B. Appendix B

H2DEH[MDP] PLF Plutonium Distribution Maps

H2DEH[MDP] PLF plutonium distribution maps were generated from digital autoradiography images. The location information was processed with the counting software in Appendix A.

Figure B-1 Plutonium distribution maps of H2DEH[MDP] PLF generated from digital autoradiography image (sample ID: 095JR2A)

Figure B-2 Plutonium distribution maps of H2DEH[MDP] PLF generated from digital autoradiography image (sample ID: 095JR2B)

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Figure B-3 Plutonium distribution maps of H2DEH[MDP] PLF generated from digital autoradiography image (sample ID: 095JR2C)

Figure B-4 Plutonium distribution maps of H2DEH[MDP] PLF generated from digital autoradiography image (sample ID: 095JR2D)

Figure B-5 Plutonium distribution maps of H2DEH[MDP] PLF generated from digital autoradiography image (sample ID: 095JR2G)

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Figure B-6 Plutonium distribution maps of H2DEH[MDP] PLF generated from digital autoradiography image (sample ID: 095JR2H)

Figure B-7 Plutonium distribution maps of H2DEH[MDP] PLF generated from digital autoradiography image (sample ID: 095JR2I)

Figure B-8 Plutonium distribution maps of H2DEH[MDP] PLF generated from digital autoradiography image (sample ID: 095JR2J)

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C. Appendix C

HDEHP PLF Plutonium Distribution Maps

HDEHP PLF plutonium distribution maps were generated from digital autoradiography images. The location information was processed with the counting software in Appendix A.

Figure C-1 Plutonium distribution map of 1:2 HDEHP PLF generated from digital autoradiography image (sample ID: 043JR2A)

Figure C-2 Plutonium distribution map of 1:2 HDEHP PLF generated from digital autoradiography image (sample ID: 043JR2B)

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Figure C-3 Plutonium distribution map of 1:2 HDEHP PLF generated from digital autoradiography image (sample ID: 043JR2C)

Figure C-4 Plutonium distribution map of 1:5 HDEHP PLF generated from digital autoradiography image (sample ID: 043JR2D)

Figure C-5 Plutonium distribution map of 1:5 HDEHP PLF generated from digital autoradiography image (sample ID: 043JR2E)

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Figure C-6 Plutonium distribution map of 1:5 HDEHP PLF generated from digital autoradiography image (sample ID: 043JR2F)

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D. Appendix D

Gamma Spectra from Mortandad Canyon Soil Samples

Figure D-1 Gamma spectrum from Mortandad Canyon soil sample (sample ID: 149JR2A)

1.E+00

1.E+01

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1.E+03

1.E+04

1.E+05

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ts

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1.E+05

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Figure D-2 Gamma spectrum from Mortandad Canyon soil sample (sample ID: 149JR2B)

Figure D-3 Gamma spectrum from Mortandad Canyon soil sample (sample ID: 149JR2C)

Figure D-4 Gamma spectrum from Mortandad Canyon soil sample (sample ID: 149JR2D)

1.E+00

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Vita

Jung Rim was born in Seoul, South Korea. His family immigrated to the USA in

1996 and settled in northern Virginia. He started full time classes as an undergraduate at

The Pennsylvania State University in Fall of 2001. He received a B.S. in Nuclear

Engineering and a B.S. in Mechanical Engineering in 2006. He continued his studies and

received a M.S. in Nuclear Engineering in 2011. Jung earned his Ph.D. in Nuclear

Engineering from The Pennsylvania State University in December of 2013. He is a

member of the American Nuclear Society (ANS), American Chemical Society (ACS),

and the Alpha Nu Sigma Society. He is married to Miel Lim. Together they have one

daughter, Aleena Rim.