advances in radiation detector materials and technologies

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Advances in Radiation Detector Materials and Technologies Research at the CRDMS is supported in part by the DOE Office of Nonproliferation Research and Development, NA-22, in the Nuclear Security Administration and in part by the Domestic Nuclear Detection Office of the Department of Homeland Security. Lynn A. Boatner Center for Radiation Detection Materials and Systems (CRDMS) Oak Ridge National Laboratory Presented at Rutgers University January 8, 2011

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Advances in Radiation Detector Materials and Technologies. Lynn A. Boatner Center for Radiation Detection Materials and Systems (CRDMS) Oak Ridge National Laboratory Presented at Rutgers University January 8, 2011. - PowerPoint PPT Presentation

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Page 1: Advances in Radiation Detector Materials and Technologies

Advances in Radiation Detector Materials and Technologies

Research at the CRDMS is supported in part by the DOE Office of Nonproliferation Research and Development, NA-22, in the Nuclear Security Administration and in part by the Domestic Nuclear Detection Office of the Department of Homeland Security.

Lynn A. BoatnerCenter for Radiation Detection Materials and Systems (CRDMS)

Oak Ridge National Laboratory

Presented at Rutgers University

January 8, 2011

Page 2: Advances in Radiation Detector Materials and Technologies

2 Managed by UT-Battelle for the U.S. Department of Energy 2 Managed by UT-Battelle for the U.S. Department of Energy

Radiation Detection by Scintillators or Electronic Materials

Scintillator Detector

IncidentRadiation

Light Output

(usually visible to near visible)

Photomultiplier

Si Photodiode

Eye

SCINTILLATION DETECTION ELECTRONIC DETECTION

Incident Radiation

Page 3: Advances in Radiation Detector Materials and Technologies

3 Managed by UT-Battelle for the U.S. Department of Energy 3 Managed by UT-Battelle for the U.S. Department of Energy

Gamma-Ray Scintillators

3 Major Processess:

ABSORPTION OF GAMMA- OR X-RAY PHOTONS AND CONVERSION INTO CHARGED PARTICLES (ELECTRON-HOLE PAIRS).

Direct process: for E> 1.02 MeV the gamma ray directly produces an electron-positron pair with the same total energy (pair production).

Compton scattering: gamma-ray energy is divided between a scattered photon and a recoil electron

Photoelectric effect: the absorbed photon generates a fast electron and a hole in a deep core level of an ion with the two carrying all of the energy of the original photon.

ENERGY TRANSFER FROM THE ELECTRONIC EXCITATIONS TO THE LUMINESCENCE CENTERS.

A complex and not well-understood process.

EMISSION OF THE SCINTILLATION PHOTONS: Occurs with a quantum efficiency Q that represents the fraction of

excited centers that actually emit a scintillation photon.

Page 4: Advances in Radiation Detector Materials and Technologies

4 Managed by UT-Battelle for the U.S. Department of Energy 4 Managed by UT-Battelle for the U.S. Department of Energy

-Ray Detection Using a Scintillation Crystal

Requirements for a Good Scintillator

1. High Light Output (Photons/Mev) NaI: Thallium 38,000 BGO 8,2002. Short Decay Time (Nano Sec)3. Wavelength Match to Detector4. High Density (>6 g/cm3)5. Chemical Stability6. Radiation Hardness7. Cost8. Crystal Growth NaI: Thallium 1948, Hufstader BGO (Bi4Ge3O12) 1973, Weber & Monchamp LSO (Lu2SiO5) 1992, Melcher & Schweitzerβ -ray to electronic excitation

S fraction transferred to luminescence centersQ quantum efficiency of the emission step

L

β

S

Q

γ

http://scintillator.lbl.gov/

Page 5: Advances in Radiation Detector Materials and Technologies

5 Managed by UT-Battelle for the U.S. Department of Energy 5 Managed by UT-Battelle for the U.S. Department of Energy

State of the Art Scintillators

Material Light Yield (photons/MeV)

Resolution @ 662keV (%)

NaI(Tl) 38,000 5.5

CsI (Tl) 65,000 6.2

BGO 8,200 12.7

LaBr3(Ce) 70,000 2.8

CeCl346,000 3.4

LSO(Ce) 39,000 7.9

SrI2 : Eu (6%) 120,000 2.7

BC-408 Plastic 10,600 -

GS-20 Li Glass ($2930 for 1-inch round, 2mm thick/ $4,739 for 6.2-inch square, 2mm thick plate)

4,100 17

Page 6: Advances in Radiation Detector Materials and Technologies

6 Managed by UT-Battelle for the U.S. Department of Energy 6 Managed by UT-Battelle for the U.S. Department of Energy

Advantages:•Low melting point → reduced temperature gradients•Size and structure match between SrI2 and EuI2 → unity distribution coefficient•High light yield, proportional → superior resolution•Congruent, since binary compound → no compositional gradients•Near-UV emission → ideal match to PMT response•Microsecond decay → enlarges dynamic range for pulse height spectrum

Among the alkaline earth halides, Strontium Iodide (Eu) possesses the most promising characteristics

Page 7: Advances in Radiation Detector Materials and Technologies

7 Managed by UT-Battelle for the U.S. Department of Energy 7 Managed by UT-Battelle for the U.S. Department of Energy

Page 8: Advances in Radiation Detector Materials and Technologies

8 Managed by UT-Battelle for the U.S. Department of Energy 8 Managed by UT-Battelle for the U.S. Department of Energy

A New Grain Selector

A new grain-selector geometry has been incorporated into the 2.5” OD Bridgman growth ampoules since it was found that two grains would sometimes propagate into the large-diameter growth chamber during the growth process – even the case of long straight grain selectors that incorporated a bulb configuration. Similar grain-selector geometries are uses in the growth of the metal and alloy single crystals – including single crystal high-performance-alloy turbine blades – for nucleation suppression.

Page 9: Advances in Radiation Detector Materials and Technologies

9 Managed by UT-Battelle for the U.S. Department of Energy 9 Managed by UT-Battelle for the U.S. Department of Energy

Strontium Iodide Eu2+ Crystal Growth

Enlarged view of the quartz frit that is used to filter the molten SrI2:Eu2+ salt that then flows into the Bridgman ampoule prior to sealing under vacuum.

Page 10: Advances in Radiation Detector Materials and Technologies

10 Managed by UT-Battelle for the U.S. Department of Energy 10 Managed by UT-Battelle for the U.S. Department of Energy

Two-inch diameter single crystal of SrI2(Eu) grown at Oak Ridge National Laboratory.

Page 11: Advances in Radiation Detector Materials and Technologies

11 Managed by UT-Battelle for the U.S. Department of Energy 11 Managed by UT-Battelle for the U.S. Department of Energy

Crystal 68f (Fisk University) was encapsulated in a standard aluminum can, and its performance is equivalent to the best RMD crystal.

Page 12: Advances in Radiation Detector Materials and Technologies

Elpasolites

• High light yield 70,000 to 180,000 ph/neutron

• High gamma equivalent >= 3 MeV

• High energy resolution 2-3%

• Pulse height discrimination

• Pulse shape discrimination

• Cubic structure

CLYC

Cs2LiYCl6

CLLC

Cs2LiLaCl6

CLLB

Cs2LiLaBr6

www.rmdinc.com

a dynasil member company

Page 13: Advances in Radiation Detector Materials and Technologies

Summary of Properties

Cs2LiLaCl6:Ce

CLLC

Cs2LiLaBr6:Ce

CLLB

Cs2LiYCl6:Ce

CLYC

Density, g/cm3 3.5 4.2 3.3

Emission, nm 290CVL, 400Ce3+ 410Ce3+

290CVL, 390Ce3+

Decay time, ns 1 CVL,60, 400, … 55, 270, …

1 CVL,40, 1800, …

Max. light yield, ph/MeV

~ 35,000 ~ 60,000 ~ 20,000

Light yieldph/n

~ 110,000 ~ 180,000 ~ 70,000

GEE, MeV ~3.1 3.2 ~3.1

Best ER @662 keV 3.4 2.9 3.9

PSD Excellent Possible Excellent

www.rmdinc.com

a dynasil member company

Page 14: Advances in Radiation Detector Materials and Technologies

Bridgman Grown Crystals

CLLC CLLB

1 in

1 in CLYC

Mel

t zo

neS

olid

ific

atio

n zo

ne

www.rmdinc.com

a dynasil member company

Page 15: Advances in Radiation Detector Materials and Technologies

CLYC: 6Li vs. natLi

0.0 0.5 1.0 1.5 2.0 2.5 3.0 3.50.0

0.5

1.0

1.5

2.0

>95% 6Li

7% 6Li (natural)

CLYC:Ce

477 keV3.3 MeV

3.4 MeVAm/Be Spectra

inte

nsi

ty,

cou

nts

/se

c/g

ram

energy, MeV

Enrichment significantly improves detection of

thermal neutrons.

www.rmdinc.com

a dynasil member company

Page 16: Advances in Radiation Detector Materials and Technologies

16 Managed by UT-Battelle for the U.S. Department of Energy 16 Managed by UT-Battelle for the U.S. Department of Energy

Investigations of alternate methods for growing large single crystals of rare-earth halide scintillators from organic solutions have led to the discovery of a new metal-organic scintillator crystal. This new scintillator material is a methanol adduct of cerium

trichloride with the formula: CeCl3(CH3OH)4.

Large transparent single crystals of this material were grown from a seeded anhydrous methanol solution in a controlled-temperature bath, and the molecular structure was subsequently determined by single-crystal x-ray structure analysis.

The CeCl3(CH3OH)4 metal-organic scintillator is applicable to x-ray, gamma-ray, alpha-

particle, and neutron detection, and this new finding offers the promise of identifying other similar metal-organic molecular systems that offer the potential for serving as efficient radiation detector materials that can potentially be grown in large sizes using solution-growth methods.

Most recently the scintillator La(4%Ce)Br3(CH3OH)4 has been discovered.

New Metal-Organic Scintillators

Page 17: Advances in Radiation Detector Materials and Technologies

17 Managed by UT-Battelle for the U.S. Department of Energy 17 Managed by UT-Battelle for the U.S. Department of Energy

Crystal Structure

Perspective view of the CeCl3(CH3OH)4 adduct showing the bridging role of the chlorine atoms. The basic CeCl3(CH3OH)4 crystal data resulting from the single crystal x-ray structural refinement are: M = 374.64, monoclinic structure, space group P21/c (no. 14), a = 8.7092(5), b = 18.5100(9), c =

8.2392(4) Å, β = 108.946(1)°, V = 1256.2(1) Å3, Z = 4, and Dcalc = 1.981 g/cm3.

Page 18: Advances in Radiation Detector Materials and Technologies

18 Managed by UT-Battelle for the U.S. Department of Energy 18 Managed by UT-Battelle for the U.S. Department of Energy

Large faceted single crystal of CeCl3(CH3OH)4 grown from an anhydrous methanol solution - shown on a cm scale. The platinum wires used to hold the seed crystal on the growth platform are visible through the crystal. Crystal growth was allowed to continue for a total growth time of 24 hrs - at which time the crystals were removed from the vessel, rinsed clean of the solution in fresh anhydrous methanol, dried, and sealed under dry inert gas.

Page 19: Advances in Radiation Detector Materials and Technologies

19 Managed by UT-Battelle for the U.S. Department of Energy 19 Managed by UT-Battelle for the U.S. Department of Energy

Energy spectrum of the CeCl3(CH3OH)4 metal-organic scintillator single crystal obtained using 662 keV gamma rays from a 137 Cs 1 Curie source. The light yield is ~ 230% of that of a BGO reference crystal - yielding a light yield of ~16,600 photons/MeV without corrections for the photomultiplier tube efficiency. The energy resolution was determined to be 11.4% for this specimen.

Energy Spectra

Page 20: Advances in Radiation Detector Materials and Technologies

20 Managed by UT-Battelle for the U.S. Department of Energy 20 Managed by UT-Battelle for the U.S. Department of Energy

X-ray Luminescence

X-ray-excited luminescence spectrum for a single crystal of CeCl3(CH3OH)4 measured in both transmission and reflection geometries using an x-ray tube operated at 35 kV as an excitation source. The peak of the luminescence occurs at ~ 365 nm.

Page 21: Advances in Radiation Detector Materials and Technologies

21 Managed by UT-Battelle for the U.S. Department of Energy 21 Managed by UT-Battelle for the U.S. Department of Energy

Transparent Polycrystalline Ceramic ScintillatorsGlass Scintillators

Why would we want these?

Single crystal growth is a time-consuming, expensive, and rate-limiting process.

Transparent polycrystalline ceramic scintillators and glass scintillators offer an alternative approach to scintillator synthesis that eliminates single crystal growth.

Page 22: Advances in Radiation Detector Materials and Technologies

22 Managed by UT-Battelle for the U.S. Department of Energy 22 Managed by UT-Battelle for the U.S. Department of Energy

Photograph of a Lu2O3:Eu ceramic excited by a 30kV continuous X-ray source.

Lu2O3:Eu

Synthesis and Post Synthesis Treatment

•Lu2O3 and Eu2O3 (5 wt. %) powders combined physically

•Powder heated in vacuum to dry

•Hot pressed at 1530°C with 262 kg/cm2 of pressure

•Annealed with flowing oxygen for 72 hours at 1050°C

Photographs of a transparent Lu2O3:Eu ceramic (~1mm thick)

Photograph of a Lu2O3:Eu ceramic before (right) and after (left) annealing in an oxygen atmosphere. Hot pressing technique tends to draw oxygen out of the host lattice, creating a dark color in the densified body. This coloration can be removed by annealing in an O2.

Page 23: Advances in Radiation Detector Materials and Technologies

23 Managed by UT-Battelle for the U.S. Department of Energy 23 Managed by UT-Battelle for the U.S. Department of Energy

LSO:Ce

Synthesis and Post-synthesis Treatment

•High quality LSO:Ce powder produced by Nichia Corporation (Japan) used

•Powder heated in vacuum to dry

•Hot pressed at 1400°C with 337 kg/cm2 of pressure for 2 hours

•Annealed in vacuum at 1050°C/108h

•Annealed in water vapor at 1050°C/32h

•Annealed in air at 1150°C/32h

Photograph of a LSO:Ce ceramic before (left) and after (right) annealing in vacuum

Photograph of an LSO:Ce ceramic (0.6 mm thick). Note that no back-light is used in this photograph.

Scanning electron microscopy (SEM) image of LSO:Ce powder from Nichia Corporation.

Transmission electron microscopy (TEM) image of LSO:Ce powder from Nichia Corporation

Particle size distribution of the Nichia LSO:Ce powder used to make the LSO ceramic.

Page 24: Advances in Radiation Detector Materials and Technologies

24 Managed by UT-Battelle for the U.S. Department of Energy 24 Managed by UT-Battelle for the U.S. Department of Energy

Scintillating pulse shape of a LSO:Ce polycrystalline ceramic excited by 662 KeV gamma photons. The solid line represents single- and three-exponential (+ noise) fits to the experimental data . The decay time constants and contribution of faster components in comparison to the decay time of about 42 ns generally accepted for single crystal LSO.

Energy spectra (for 662 keV excitation photons) of the LSO:Ce refernce crystal (the light yield for this crystal was ~30,000 photons/MeV) and the LSO:Ce ceramic at various post-sintering annealing stages. Symbol “A” denotes a ceramic with a 2 mm thickness after annealing in vacuum, “A1” denotes a 0.7 mm thick piece of the former ceramic after additional annealing in water vapor, and “A1a” the same after additional annealing in air.

Page 25: Advances in Radiation Detector Materials and Technologies

25 Managed by UT-Battelle for the U.S. Department of Energy 25 Managed by UT-Battelle for the U.S. Department of Energy

New scintillators for gamma ray spectroscopy developed for DHS and DOE. (upper left) SrI2(Eu) single crystal under UV excitation, (upper right) GYGAG(Ce) ceramic, (bottom) two Bi-loaded polymers under UV excitation.

Comparative Gamma Spectroscopy with SrI2(Eu), GYGAG(Ce) and Bi-loaded Plastic Scintillators N.J. Cherepy, Member, IEEE, S.A. Payne, Member, IEEE, B.W. Sturm, Member, IEEE, J.D. Kuntz, Z.M. Seeley, B.L. Rupert, R.D. Sanner, O.B. Drury, T.A. Hurst, S.E. Fisher, M. Groza, L. Matei, A. Burger, Member, IEEE, R. Hawrami, Member, IEEE, K.S. Shah, Member, IEEE, and L.A. Boatner

IEEE Transactions on Nuclear Science, IEEE/NSS Proceedings 2010 (Submitted for publication)

Page 26: Advances in Radiation Detector Materials and Technologies

26 Managed by UT-Battelle for the U.S. Department of Energy 26 Managed by UT-Battelle for the U.S. Department of Energy

Composition(Glass-forming space)Cladding Phosphate

Lead PhosphateSilicate

GermanateArsenate

GLASS SCINTILLATORS HOW CAN WE IMPROVE THEIR PERFORMANCE?

Glass Scintillator Parameter Space

ActivationCe,Pr,Nd,Eu,Tb,Yb

Co-doping

Post-synthesis TreatmentTime

TemperatureAtmosphere

Structure *Phosphate glass only

Phosphate chain length

* B. C. Sales, J. O. Ramey, L. A. Boatner, and J. C McCallum, “Structural in equivalence of the Ion-Damaged-Produced Amorphous State and the Glass State in Lead Pyrophosphate,” Phys. Rev. Lett. 62, (10) 1138-1141 (1989).

Page 27: Advances in Radiation Detector Materials and Technologies

27 Managed by UT-Battelle for the U.S. Department of Energy 27 Managed by UT-Battelle for the U.S. Department of Energy

137Cs 1μCi γ source

662 keV γ photons

0.5 μs shaping time

Energy Spectra of Ce Doped Ca-Na Phosphate Glasses

Page 28: Advances in Radiation Detector Materials and Technologies

28 Managed by UT-Battelle for the U.S. Department of Energy 28 Managed by UT-Battelle for the U.S. Department of Energy

Current Uses of 3He

Cryogenics below 1 K, laser research, guided missilesNo known alternative

Medical imaging of lungsUnique capability

Security applicationsLooking for alternatives

Oil well loggingNeed alternatives

NonproliferationLow probability of finding alternatives

Neutron polarizationNo known alternatives

Neutron scattering detectorsNeed alternatives for large area coverage

Ron Cooper 29 September, 2009

Page 29: Advances in Radiation Detector Materials and Technologies

29 Managed by UT-Battelle for the U.S. Department of Energy 29 Managed by UT-Battelle for the U.S. Department of Energy 29

Gas Detectors MeVHHHen 76.0133 barns5333

~25,000 ions and electrons (~4x10-15 coulomb) produced per neutron

Anode

Cathode

- +

Fill gas

Gas Proportional Counter

radius

E-field

HV

R

1. 1 part in 104 of natural helium2. Obtained from Tritium decay

1. 3T →  3He  + e- + antineutrino2. Half-life is 12.3 years

3. Tritium is produced in reactors mainly for nuclear weapons

4. The Watts-Bar reactor, near Oak Ridge - scheduled for tritium production - delayed

5. Accelerator option, 40 3MeV accelerators with 1A beam current each, -20k liters/year 120MW of beam power!

Page 30: Advances in Radiation Detector Materials and Technologies

30 Managed by UT-Battelle for the U.S. Department of Energy 30 Managed by UT-Battelle for the U.S. Department of Energy

Alternative Thermal Neutron Converters

6Li(n,α) reaction:n + 6Li → 3H + 4He Q-value=4.78 MeVE3H=2.73 MeV E4He=2.05 MeVCross Section → 940 b6LiF coatings - Chemical StabilityRanges: 3H-32.1 microns; 4He-6.11 microns nabs-174 microns 10B(n,α) reaction:n + 10B → 4He + 7Li [ground state] Q-value=2.792 MeVn + 10B → 4He + 7Li [excited state] Q-value=2.310 MeVELi =0.84 MeV E4He =1.47 MeVCross Section → 3836 b10B coatingsRanges: 7Li-1.6 microns; 4He-3.6 microns nabs -19.9 microns

Boron straws10BF3 (gas)

Other reactions:157Gd(n,γ) (Natural Gd, cross section 49,000 b)113Cd(n,γ)Less useful gamma-rays and conversion electrons

Range calculations: McGregor, D. S., et al., NIM A 500 (2003) 272-308

The challenge is to balance thermal neutron conversion efficiency and charged particle transport (while minimizing and/or rejecting gamma-ray response)

Page 31: Advances in Radiation Detector Materials and Technologies

31 Managed by UT-Battelle for the U.S. Department of Energy 31 Managed by UT-Battelle for the U.S. Department of Energy

Prototype 6Li-lined gas detector that incorporates a Li-coated Mo cathode, a 0.001” stainless steel anode wire, and a Xe fill gas at one atmosphere.

Page 32: Advances in Radiation Detector Materials and Technologies

32 Managed by UT-Battelle for the U.S. Department of Energy 32 Managed by UT-Battelle for the U.S. Department of Energy

Typical preamplifier output pulse from a neutron interaction. Note the large amplitude of the pulse, which after subsequent amplification in a spectroscopy amplifier, leads to a count in the neutron “peak” (>channel number 1000) shown in the pulse height spectra.

Page 33: Advances in Radiation Detector Materials and Technologies

33 Managed by UT-Battelle for the U.S. Department of Energy 33 Managed by UT-Battelle for the U.S. Department of Energy

DETAILS OF THE NEUTRON RESPONSE PORTION OF THE PULSE HEIGHT SPECTRA ARE SHOWN FOR THE 6Li-LINED PROPORTIONAL COUNTER USING AN AmLi MODERATED NEUTRON SOURCE -- UNSHIELDED SOURCE (BLACK), A 2” THICK Pb-SHIELDED SOURCE (BLUE), AND FOR A Cd-SHIELDED SOURCE (RED).