Safety analyses at the high flux isotope reactor (HFIR) are required to qualify irradiation of production targets containing neptunium dioxide/aluminum cermet (NpO2/Al) pellets for the production of plutonium-238 (238Pu). High heat generation rates (HGRs) due to a fertile starting material (237Np), low melting temperatures, and previously unstudied material irradiation behavior (i.e., swelling/densification, fission gas release) require a sophisticated set of steady-state thermal simulations in order to ensure sufficient safety margins. Experience gained from previous models for preliminary target designs is incorporated into a more comprehensive production target model designed to qualify a target for three cycles of irradiation and illuminate potential in-reactor behavior of the target.
Issue Section:
Research Papers
References
1.
Hurt
, C. J.
, Freels
, J. D.
, Jain
, P. K.
, and Maldonado
, G. M.
, “Thermo-Mechanical Safety Analyses of Preliminary Design Experiments for 238Pu Production
,” ASME J. Nucl. Eng. Radiat. Sci.
(in press).2.
Hurt
, C. J.
, Freels
, J. D.
, Hobbs
, R. W.
, Jain
, P. K.
, and Maldonado
, G. M.
, 2016
, “Thermal Safety Analyses for the Production of Plutonium-238 at the High Flux Isotope Reactor
,” Oak Ridge National Laboratory, Oak Ridge, TN, Technical Report No. ORNL/TM-2016/234
.3.
Hurt
, C. J.
, Freels
, J. D.
, Griffin
, F. P.
, Chandler
, D.
, Hobbs
, R. W.
, and Wham
, R. M.
, 2015
, “Safety Analysis Models for the Irradiation of 237 Np Targets at the High Flux Isotope Reactor
,” Nuclear and Emerging Technologies for Space (NETS)
, Albuquerque, NM
, Feb. 23–26
, pp. 20
–29
.4.
Freels
, J. D.
, Jain
, P. K.
, and Hobbs
, R. W.
, 2012
, “Design and Nuclear-Safety Related Simulations of Bare-Pellet Test Irradiations for the Production of Pu-238 in the High Flux Isotope Reactor Using COMSOL
,” COMSOL Conference
, Boston, MA
, Oct. 3–5
.5.
COMSOL Multiphysics (R), 2015, “
COMSOL Multiphysics® v. 5.2
,” COMSOL AB, Stockholm, Sweden.6.
Hurt
, C. J.
, Wham
, R. M.
, Hobbs
, R. W.
, Owens
, R. S.
, Chandler
, D.
, Freels
, J. D.
, and Maldonado
, G. M.
, 2014
, “Plutonium-238 Production Target Design Studies
,” Institute of Nuclear Materials Management 55th Annual Meeting
, Atlanta, GA
, July 20–24
, pp. 1111
–1120
.7.
Oak Ridge National Laboratory
, 2014
, “Thermal and Hydraulic Design
,” HFIR Updated Safety Analysis Report, Revision 14, Oak Ridge National Laboratory
, Oak Ridge, TN, Report No. ORNL/HFIR/USAR/2344.8.
Wham
, R. M.
, Felker
, L. K.
, Collins
, E. D.
, Benker
, D. E.
, Owens
, R. S.
, Hobbs
, R. W.
, Chandler
, D.
, and Vedder
, R. J.
, 2014, “The 238Pu Supply Project
,” The 19th Pacific Basin Nuclear Conference
, Vancouver, BC
, Aug. 24–28
, pp. 643
–651
.9.
Wham
, R. M.
, DePaoli
, D. W.
, and Hobbs
, R. W.
, 2015
, “Reestablishing the Supply of Plutonium-238
,” Transactions of the American Nuclear Society
, Vol. 113, Washington, D.C.
, pp. 205
–206
.10.
Griffin
, F. P.
, 2017
, “RELAP5 Consolidated Model of High Flux Isotope Reactor System
,” ORNL Report, Revision 2, Oak Ridge National Laboratory, Oak Ridge, TN, Report No. ORNL/RRD/INT-154.11.
Chandler
, D.
, 2015
, “Neutronics Simulations of 237 Np Targets to Support Safety-Basis and 238Pu Production Assessment Efforts at the High Flux Isotope Reactor
,” Nuclear and Emerging Technologies for Space 2015 (NETS)
, Albuquerque, NM
, Feb. 23–26
, pp. 40
–49
.12.
Chandler
, D.
, 2016
, “Development of an Efficient Approach to Perform Neutronics Simulations for Plutonium-238 Production
,” PHYSOR Conference
, Sun Valley, Idaho
, May 1–5
, pp. 913
–927
.13.
Madhusudana
, C. V.
, 1995
, Thermal Contact Conductance
, Springer-Verlag
, New York
.14.
Ullman
, A.
, Acharya
, R.
, and Olander
, D. R.
, 1974
, “Thermal Accommodation Coefficients of Inert Gases on Stainless Steel and UO2
,” J. Nucl. Mater.
, 51
(2
), pp. 277
–279
.15.
Thomas
, L. B.
, and Loyalka
, S. K.
, 1982
, “Determination of Thermal Accommodation Coefficients of Inert Gases on a Surface of Vitreous UO2 at ∼35 °C
,” Nucl. Technol.
, 59
(1
), pp. 63
–69
.16.
Hall
, R. O. A.
, and Martin
, D. G.
, 1987
, “The Evaluation of Temperature Jump Distances and Thermal Accommodation Coefficients From Measurements of the Thermal Conductivity of UO2 Packed Sphere Beds
,” Nucl. Eng. Des.
, 101
(3
), pp. 249
–258
.17.
Rohsenow
, W. M.
, Hartnett
, J. P.
, and Ganic
, E. N.
, 1985
, Handbook of Heat Transfer Fundamentals
, 2nd ed., McGraw-Hill Book
, New York
.18.
Bondi
, A.
, 1964
, “Van Der Waals Volumes and Radii
,” J. Phys. Chem.
, 68
(3
), p. 441
.19.
Van Atta
, C. M.
, 1965
, Vacuum Science and Engineering
, 1st ed., McGraw-Hill
, New York
, pp. 440
–441
.20.
Hirschfelder
, J.
, Curtiss
, C.
, and Bird
, R.
, 1954
, Molecular Theory of Gases and Liquids
, 1st ed., Wiley
, New York
, p. 1110
.21.
Brokaw
, R. S.
, 1958
, “Approximate Formulas for Viscosity and Thermal Conductivity for Gas Mixtures
,” J. Chem. Phys.
, 29
(2
), pp. 391–397.22.
Saxena, S. C.,
1957
, “Thermal Conductivity of Binary And Ternary Mixtures of Helium, Argon, and Xenon
,” Indian J. Phys, Vol. 31, pp. 597-606.23.
Hoffman
, G. L.
, Rest
, J.
, and Snelgrove
, J. L.
, 1996
, “Irradiation Behavior of Uranium Oxide—Aluminum Dispersion Fuel
,” International Meeting for Reduced Enrichment for Research and Test Reactors
, Seoul, Korea
, Oct. 7–10
.24.
Assmann
, H.
, and Stehle
, H.
, 1978
, “Thermal and in-Reactor Densification of UO2: Mechanisms and Experimental Results
,” Nucl. Eng. Des.
, 48
(1
), pp. 49
–67
.25.
Yanagisawa
, K.
, 1986
, “Fuel Densification and Swelling: Relationship Between Burn-Up Induced Axial and Radial Fuel Dimensional Changes
,” Nucl. Eng. Des.
, 96
, pp. 11
–20
.26.
Meyer
, R. O.
, 1976
, “The Analysis of Fuel Densification—Aluminum Dispersion Fuel
,” Office of Nuclear Regulatory Commission, Washington, D.C., Report No. NUREG-0085.27.
Griffin
, F. P.
, 2013
, “RELAP5 Transient Analyses of Pu-238 Fully-Loaded Targets
,” Oak Ridge National Laboratory, Oak Ridge, TN, Report No. ORNL/TM-2016/234.28.
Howard
, R. H.
, Miller
, J. H.
, Owens
, R. S.
, Hemrick
, J. G.
, Erdman
, D. L.
, III, Schmidlin
, J. E.
, and Hawkins
, C. S.
, 2014
, “Mechanical and Thermal Properties for 237 Np Pellets to Support 238Pu Production
,” The Nuclear Materials Conference—NuMat2014
, Clearwater, FL
, Oct. 27–30
.29.
Marquardt
, E. D.
, Le
, J. P.
, and Radebaugh
, R.
, 2000
, “Cryogenics Material Properties Database
,” 11th International Cryocooler Conference
, Keystone, CO
, June 20–22
, pp. 681
–687
.30.
U.S. Department of Defense
, 1998
, “Metallic Materials and Elements for Aerospace Vehicle Structures, Department of Defense
,” Military Handbook
, Wright-Patterson AFB, OH.31.
ASM International
, 1992
, ASM Handbook
, Vol. 2
, ASM International
, Novelty, OH
.32.
Lalpoor
, M.
, Eskin
, D. G.
, and Katgerman
, L.
, 2009
, “Cold-Cracking Assessment in AA7050 Billets During Direct-Chill Casting by Thermomechanical Simulation of Residual Thermal Stresses and Application of Fracture Mechanics
,” Metall. Mater. Trans. A
, 40A
(13
), pp. 3304
–3313
.33.
Sharma
, S. C.
, 2000
, “Effect of Albite Particles on the Coefficient of Thermal Expansion Behavior of the Al6061 Alloy Composites
,” Metall. Mater. Trans. A
, 31A
(3
), pp. 773
–780
.34.
Sakai
, K.
, Matsumuro
, A.
, and Senoo
, M.
, 1996
, “Elastic Moduli of Al–Li Alloys Treated at a High Pressure of 5.4 GPa
,” J. Mater. Sci.
, 31
(12
), p. 3309
.35.
Naimon
, E. R.
, Ledbetter
, H. M.
, and Weston
, W. F.
, 1975
, “Low-Temperature Elastic Properties of Four Wrought and Annealed Aluminium Alloys
,” J. Mater. Sci.
, 10
(8
), p. 1309
.36.
McLellan
, R. B.
, and Ishikawa
, T. J.
, 1987
, “The Elastic Properties of Aluminum at High Temperatures
,” J. Phys. Chem. Solids
, 48
(7
), p. 603
.37.
Stokes
, H. J.
, 1960
, “Computer for the Identification of Charged Particles
,” Sci. Instrum.
, 37
(7
), p. 768
.38.
MatWeb, 1999,
“Material Property Data
,” MatWeb, Blacksburg, VA, accessed Sept. 11, 2018, http://www.matweb.com39.
Ho
, C. Y.
, Powell
, R. W.
, and Liley
, P. E.
, 1972
, “Thermal Conductivity of the Elements
,” J. Phys. Chem. Ref. Data
, 1
(2
), p. 279
.40.
McBride
, B. J.
, Gordon
, S.
, and Reno
, M. A.
, 1993
, “Thermodynamic Data for Fifty Reference Elements
,” National Aeronautics and Space Administration, Washington, DC, Technical Report No. NASA/TP-3287
.https://ntrs.nasa.gov/search.jsp?R=2001002111641.
Ramires
, M. L. V.
, Nieto de Castro
, C. A.
, Nagasaka
, Y.
, Nagashima
, A.
, Assael
, M. J.
, and Wakeham
, W. A.
, 1995
, “Standard Reference Data for the Thermal Conductivity of Water
,” J. Phys. Chem. Ref. Data
, 24
(3
), p. 1377
.42.
Lide
, D. R.
, ed., 1998
, CRC Handbook of Chemistry and Physics
, 79th ed., CRC Press, Boca Raton, FL, pp. 6
–3
.43.
Pankratz
, L. B.
, 1982
, “Thermodynamic Properties of Halides
,” U.S. Bureau of Mines Bulletin 672.44.
Kestin
, J.
, Sokolov
, M.
, and Wakeham
, W. A.
, 1978
, “Viscosity of Liquid Water in the Range −8 °C to 150 °C
,” J. Phys. Chem. Ref. Data
, 7
(3
), p. 941
.45.
Incropera
, F. P.
, and DeWitt
, D. P.
, 2002
, Fundamentals of Heat and Mass Transfer
, 6th ed., Wiley, John Wiley & Sons, Inc.
, Hoboken, NJ
.46.
Griess
, J. C.
, Savage
, H. C.
, and English
, J. L.
, 1961, “Effect of Heat Flux on the Corrosion of Aluminum by Water—Part III: Final 49 Report on Tests Relative to the High-Flux Isotope Reactor
,” Oak Ridge National Laboratory, Oak Ridge, TN, Technical Report No. ORNL-3230.47.
Farrell
, K.
, and King
, R. T.
, 1979
, “Tensile Properties of Neutron-Irradiated 6061 Aluminum Alloy in Annealed and Precipitation-Hardened Conditions
,” American Society for Testing and Materials, West Conshohocken, PA, Standard No. ASTM STP 683
.48.
Hobbs
, R. W.
, Chandler
, D.
, Hurt
, C. J.
, Freels
, J. D.
, Owens
, R. S.
, and Bryan
, C.
, 2015
, “Potential Improvements to 238Pu Production Targets for the High Flux Isotope Reactor
,” ANS Winter Meeting
, Washington, DC
, Nov. 8–12
, pp. 207
–210
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