high flux isotope reactor operation and capabilities

Managed by UT-Battelle for the Department of Energy

Ronald A. Crone Research Reactors Division Director

Presented by: Chris Bryan Irradiations Manager

High Flux Isotope Reactor

June 10, 2013

High Flux Isotope Reactor Operation and Capabilities

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

ORNL is US DOE’s largest science and energy laboratory and HFIR is integrated with ORNL’s S&T missions


$1.65B budget

4,650 employees

3,000 research guests

annually

3 Managed by UT-Battelle for the Department of Energy

Oak Ridge National Laboratory Manhattan Project initiates a long history of ORNL Research Reactors

13 RESEARCH REACTORS, STARTING WITH THE GRAPHITE REACTOR IN 1943

Graphite Reactor Tower Shielding Reactor Health Physics Research Reactor Molten Salt Reactor Experiment

Oak Ridge Research Reactor


The need for HFIR was expressed by Glenn Seaborg in 1957

“The field of new transuranium elements is entering an era where the participating scientists in this country cannot go much further without some unified national effort… The future progress in this area depends on substantial weighable quantities (say milligrams) of berkelium, californium, and einsteinium…” G. T. Seaborg Berkeley, October 24, 1957

Fm

Es

Fm 254 Fm 255 Fm 256

SF

Fm 257

Es 254 Es 255

- EC -

CfCf 249

, (n,f)

Cf 250 Cf 251 Cf 253 Cf 254

, ,

, (n,f) ,

Bk 249Bk

Bk 250 Bk 251

-

Cm 242

Am

Cm

Pu 246

Cm 243

Pu 239

, (n,f)

, (n,f)

Cm 244 Cm 245

, (n,f)

Cm 246

, (n,f)

Cm 247

, SF

Cm 248

SF

Cm 249 Cm 250

Pu 240

Np 237

Pu 238 Pu 241 Pu 242 Pu 243

Np 238

Pu 244 Pu 245

-, (n,f)

, (n,f)-

Am 241

, EC-

Am 242 Am 243 Am 244 Am 245 Am 246

94

93

95

96

N

Z

98

97

100

99

SF

--

-

---

- - -Pu

Np

Es 253

Cf 252

, SF


HFIR History


Materials Irradiation Testing • Fusion Energy – provides best available neutron

spectrum for radiation damage testing on fusion components; collaboration between U.S. and Japan for over thirty years

• Fission Energy – research supporting next-generation commercial power reactors including accident tolerant fuel and reactor materials

•National Security – Neutron Activation Analysis supporting IAEA non-proliferation monitoring 1,021 Materials and NAA Irradiations in FY2011

Reliable Source of Unique Isotopes •Californium-252 – HFIR supplies 80% of the world

demand, which is critical for industrial, defense, and energy uses

•Berkelium-249 – used in the discovery of element 117 and the search for element 119

•Plutonium-238 – the source of power for satellites and NASA’s deep space missions

• Selenium-75, Nickel-63, Tungsten-188 – supplier of industrial, homeland security, and medical isotopes 98 Commercial and Medical Isotope Irradiations

in FY2011

Neutron Scattering •Cold Source

• Small-angle neutron scattering (2) • Cold triple-axis spectroscopy • Neutron imaging • Quasi-Laue Diffractometer

•Thermal beams • Triple-axis spectroscopy (3) • Powder diffraction • Single-crystal diffraction • Residual stress diffraction

1,300 Users conducted 730 Unique Neutron Scattering Experiments in FY2011

For more information go to http://neutrons.ornl.gov/facilities/HFIR/

HFIR capabilities serve a broad range of science

and technology communities

•Very high flux – available for neutron science in the world at 2.5X1015N/cm2/sec

• Fuel design – breakthrough flux-trap design remains world class

173 Neutron Scattering and Material Science Publications in CY2011

http://neutrons.ornl.gov/facilities/HFIR/


Reactor Characteristics Vertical Cross Section of HFIR

Power level: 85 MW

Light water moderated and cooled Beryllium reflected

Fuel: AL clad U3O8 plates – 9.4 Kg 235U

Control – concentric cylinders of EuO

Pressure vessel – carbon steel with stainless steel cladding (94“ I.D. x 2-7/8“ thick)

Coolant flow: 16,000 GPM

Inlet pressure: 468 PSIG: Temp: 120º F

Outlet pressure: 358 PSIG: Temp: 156º F

Fuel cycle: 23-27 days (@85 MW operations)


HFIR is a series of concentric cylindrical features

Target

Fuel

Control

Reflector


HFIR offers a variety of irradiation sites, each with unique characteristics

Target RB* Small VXF Large VXF

Fast flux, E > 0.1 MeV (1018 n/m2-s; 1014 n/cm2-s) 11 5.3 0.51 0.13

Peak displacements per atom (dpa) per calendar year (stainless steel) 12.6 4.7 0.45 0.12

Thermal flux (1018 n/m2-s; 1014 n/cm2-s) 20 9.7 7.5 4.3

Gamma heating (W/g SS) 46 16 3.3 1.7 Typical capsule diameter (mm) 13 43 37 69 Number of available positions 36 8 16 6


Top View of Reactor Irradiation Sites

Inner

Fuel Element

Target Basket

VXF

Removable Beryllium Reflector

Outer Fuel

Element

Permanent Beryllium Reflector


HFIR Hydraulic Tube Facility allows online insertion and removal of experiments during the cycle. • Allows access to the high flux region

with the reactor operating

• Can accommodate 9 capsule targets (rabbits)

Overall Dimensions of a Finned Rabbit


Beryllium Reflector offers larger volume for experiments/isotope production

• Suitable for isotope production (C-14, Pu-238)

• Lower flux and gamma rates well suited for fuels testing.

• Lower Fast flux not ideal for radiation-induced damage (DPA), but still high


Involute shaped fuel plates offer constant width water gap, critical to fuel performance.

171 Fuel

Plates

369 Fuel

Plates

Flux Trap

Region

447 cycles X 540 fuel plates = 241,380 fuel plates without a failure. Excellent design and quality control by the fabricator.


HFIR neutron scattering facilities HB-1, Polarized Triple-Axis Spectrometer

HB-1A, Fixed Incident Energy Triple-Axis Spectrometer

HB-2A, Neutron Powder Diffractometer

HB-2B, NRS2 – Neutron Residual Stress Mapping Facility

HB-2C, WAND – U.S.-Japan Wide-Angle Neutron Diffractometer

HB-3, Triple-Axis Spectrometer

HB-3A, Single-Crystal Four-Circle Diffractometer

CG-1 Development Beam Line

CG-2, SANS1 – Small-Angle Neutron Scattering Diffractometer

CG-3, BIO-SANS – Biological Small-Angle Neutron Scattering Instrument

CG-4C, U.S.-Japan Cold Neutron Triple-Axis Spectrometer

CG-4 D, IMAGINE – Image Plate Single Crystal Diffractometer


In-Core irradiation studies

HFIR is being used to explore composites for nuclear applications

Spectrum tailoring provides data for fusion reactor material down-selection

17J capsule prior to Li fill

MATERIALS RESEARCH FUEL RESEARCH

Accident-tolerant nuclear reactor fuel

Fully ceramic microencapsulated fuel has these benefits:

• Insignificant hydrogen production: No need for 1200°C limit to prevent Zr-steam reaction

• No core melt in severe accidents • Highly resistant to fission product release

in anticipated operational occurrences • Better economy (more watts per gram of U) • Higher power ramp capability • Potential drop-in fuel for current LWR fleet • Simplify next-generation reactor design

TRISO fuel particle which has been cracked, showing the

multiple coating layers


In-Core isotope production HFIR produces a diverse set of isotopes for a variety of industries and applications

Isotope Production

• Cf-252: Rx startup source, radiography for well-logging, coal mining and oil pipelines

• W-188 : Bone pain palliation, tumor therapy, restenosis therapy, bone marrow ablation, and treatment of skin cancer

• Se-75 : gamma radiography • Lu-177 : Microstatic tumor therapy and

bone pain palliation • Ni-63 : Detection of explosives and

drugs at airports • Ho-166m : Reference sources for

ionization chambers • Bk-249 : Instrumental in the discovery

of element 117

New Isotopes in 2012

• U-234 : Fission chambers • Ir-192 : Therapy • Ac-225 : Therapy • Cl-36 : Tracer • Gd-152 Battery

Planning in progress for

• Pu-238 production at HFIR/REDC & ATR • Ho-166m : Various • C-14 : Tracer

Energy •Nuclear fuel quality control •Reactor start-up sources •Coal analyzers •Oil exploration

Security •Handheld contraband detectors •Standard for all neutron fission measurements •Monitoring downblending of HEU •Identifying unexploded chemical ordnance & detecting land mines

Industrial •Mineral analyzers •Cement analyzers •FHA measurements for corrosion (bridges, highway infrastructure)


ORNL/INL re-establishing DOE capability to produce 238Pu for NASA space missions NASA missions rely on several methods for generating electricity in space. Recent work at ORNL has focused on a 2-year plan for developing and proving the technologies to produce 238Pu to satisfy NASA’s needs. 238Pu is produced by neutron capture of 237Np (Neptunium) in a high thermal flux nuclear reactor. ORNL’s High Flux Isotope Reactor and INL’s Advanced Test Reactor will perform the irradiations, and ORNL’s Radiochemical Engineering Development Center will process the resulting material, extracting the purified 238Pu.

Mars Rover Curiosity uses an RTG containing 3.6kg 238Pu to produce electricity. -NASA image ORNL’s research reactors division will lead the efforts to

design and qualify irradiation targets, beginning with small single-pellet capsules (237Np oxide pellets) and progressing towards multi-pellet targets to verify both safety calculations as well as product quality estimates. The result of this 2-year effort will be include specifications, designs, processes and procedures required to produce 238Pu at a pilot scale as well as a schedule and cost for increasing production to full-scale (1.5-2 kg per year)

Image of a single 0.25” diameter

237Np pellet

Multi Mission Radio Thermoelectric Generator (MMRTG) -NASA image

238Pu pellet glowing from internal heat after being

insulated


The HFIR Gamma Irradiation Facility (GIF) is used for accelerated radiation damage studies.

Primary Uses

• Qualify materials and components for the nuclear industry

• Understand material behaviors in a radiation environment

Capabilities

• Samples can be subjected to gamma fluxes up to 108Rad/h.

• Samples are placed in a 3-in diameter X 25” long canister in the flux trap of a spent fuel element.

• Sweep gasses provide cooling and inert environment.

• Electrical connections allow data acquisition and power to the samples.

Ion exchange resin radiation tolerance studies (for removing Cs-137 from high level waste)

Investigating radiation resistance of materials for lunar reactor environments (NASA)

Understanding radiation induced conductivity changes in high voltage insulators


Gamma irradiations will help FDA’s understanding of spinal disk properties

Side view of artificial spinal disc (Graphic from www.knowyourback.org )

Artificial Spinal Discs As an alternative to spinal fusion, new advances are allowing the replacement of damaged or worn intervertebral discs with artificial discs. The contacting portion of the artificial disc are typically produced from a variant of polyethylene, an inert, biocompatible material that provides both cushioning and wear characteristics. Wear characteristics are of particular concern, since over time the polyethylene material can be worn thin, and cause buildup of polyethylene dust, ultimately leading to failure of the artificial joint. All medical devices and prostheses are treated with gamma radiation prior to installation. This serves two purposes: 1) to sterilize the material and 2) gamma radiation improves the wear characteristics of the polyethylene. The Food and Drug Administration (FDA) has undertaken a project to better characterize the wear properties of the contacting disc materials. This involves irradiating disc samples at varying gamma rates and to different total gamma exposures. RRD has recently completed irradiation of the first series of samples and will continue with additional samples in the coming weeks and months.

For more information on spinal disc replacement, please see http://www.cedars-sinai.edu/Patients/Programs-and-Services/Spine-Center/Services/Surgical-Treatments/Artificial-Disc-Replacement.aspx

Several varieties of artificial spinal discs

http://www.knowyourback.org/

http://www.cedars-sinai.edu/Patients/Programs-and-Services/Spine-Center/Services/Surgical-Treatments/Artificial-Disc-Replacement.aspx


HFIR NAA facilities support a wide variety of applications

Typical HFIR NAA

Applications

Impurities analysis

Environmental studies

Criminal forensics

Nuclear forensics

Geology

Two Pneumatic Tubes: PT-1: Thermal Neutron Flux: 4 × 1014 n cm-2 s-1 • Thermal-to-Resonance Ratio: 35 • Shielded sample loading station with remote

manipulators • Decay station in pool • Rabbit travel time: 2.5 seconds PT-2: Thermal Neutron Flux: 4 × 1013 n cm-2 s-1 • Thermal-to-Resonance Ratio: 250 • Loading station in hood • Automated delayed-neutron counting station that

will measure 20 - 30 picograms of 235U or other fissile material in 5 minutes

• Other characteristics of PT-1 apply


ORNL Hot Cell facilities have capabilities that are directly coupled to HFIR

Radiochemical Processing Facility (REDC)

•Pellet forming, Welding, Hydrostatic compression, encapsulation

•Dissolution, voloxidation, solvent extraction, ion exchange processing, evaporation, filtration, precipitation, furnace heating.

•Analytical chemistry, radiography, Helium leak testing, Physical and dimensional inspection, Calorimetry

•Alpha laboratory

Irradiated Materials Examination and Testing

(IMET) •Metrology, profilometry, physical

examination •High temp, high vacuum testing •Tensile testing in various

environments. • Impact testing, fatigue and

fracture toughness testing •Highly radioactive material

characterization • SEM •Machining, CNC milling, welding,

ultrasonic cleaning •Annealing

Irradiated Fuels Examination Laboratory

(IFEL) • Full-length LWR fuel examination •Repackaging of spent fuel •Metrology, metallography,

grinding/polishing, optical and electron microscopy, gamma spectrometry

• Fission gas sampling and analysis •Thermal imaging • SEM/Microprobe •Microsphere gamma analyzer for

individual fuel particle analysis

high flux isotope reactor operation and capabilities

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