Accelerating nuclear fuel development and qualification: Modeling and simulation integrated with separate-effects testing
Source abstract
Abstract
Abstract An approach to transform and accelerate nuclear fuel development and qualification is outlined. The approach exploits advanced modeling and simulation at the outset to inform constituent and system selection and to enable integral fuel performance analyses. Analyses using these tools identify and prioritize the most important fuel performance parameters and phenomena for subsequent targeted characterization with separate-effects tests. Separate-effects testing spans out-of-pile and in-pile tests and is meant to iterate with and inform engineering-scale integral fuel performance analyses throughout the development process. Exercising this cycle in an agile fashion will increase confidence in the integral fuel performance predictions while reducing uncertainties. This process sets the stage for executing a much more limited set of well-defined integral irradiation tests designed to validate engineering-scale fuel performance codes and to confirm the performance and safety of the fuel system under prototypic conditions. This approach will reduce the time for development and qualification of a new fuel system, and it will also reduce associated costs.
Source: openaire · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Nuclear Materials and Properties · Nuclear reactor physics and engineering · Nuclear and radioactivity studies
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (96)
Show source-provided references
1. Wigner · 1942
2. Radiation chemistry10.1021/j150452a029 ↗
3. Leyse · 1951
4. Weinberg · 1994
5. Holl · 1997
6. Barrie · 1955
7. Marshall · 1954
8. Hot cell for testing MTR-irradiated specimens
9. Effects of high burn-up on oxide ceramic fuels
10. Performance of metallic fuels and blankets in liquid-metal fast breeder reactors10.13182/NT84-A33408 ↗
11. The early history of high-temperature helium gas-cooled nuclear power reactors10.1016/0360-5442(91)90084-Y ↗
12. An approach to fuel development and qualification10.1016/j.jnucmat.2007.05.029 ↗
13. EPRI and the zero fuel failures program
14. The DOE advanced gas reactor fuel development and qualification program
15. Matzke · 1986
16. The materials of fast breeder reactors10.1007/BF01054687 ↗
17. Wachs · 2007
18. Saunders · 1998
19. A conceptual model for the fuel oxidation of defective fuel10.1016/j.jnucmat.2006.12.050 ↗
20. Corrosion of zirconium alloys used for nuclear fuel cladding10.1146/annurev-matsci-070214-020951 ↗
21. Thermodynamic and kinetic aspects of carbon transport in sodium-steel systems10.1016/0022-3115(70)90087-5 ↗
22. Oxidation of PCEA nuclear graphite by low water concentrations in helium10.1016/j.jnucmat.2014.07.009 ↗
23. Effects of low-pressure oxidation on the surface composition of single crystal silicon carbide10.1111/j.1551-2916.2005.00357.x ↗
24. A review of steel corrosion by liquid lead and lead–bismuth10.1016/j.corsci.2009.03.013 ↗
25. Uniform corrosion of FeCrAl alloys in LWR coolant environments10.1016/j.jnucmat.2016.06.047 ↗
26. Baker · 1962
27. Protective coatings on zirconium-based alloys as accident-tolerant fuel (ATF) claddings10.1515/corrrev-2017-0010 ↗
28. Performance of FCCI barrier foils for U–Zr–X metallic fuel10.1016/j.jnucmat.2009.03.011 ↗
29. Microencapsulated fuel technology for commercial light water and advanced reactor application10.1016/j.jnucmat.2012.05.021 ↗
30. Taleb · 2012
31. Rickover · 1953
32. Strasser · 1982
33. Steam oxidation of fuel in defective LWR rods10.1016/S0022-3115(98)00759-4 ↗
34. Thirty years of fuels and materials information from EBR-II10.1016/S0022-3115(98)00760-0 ↗
35. Fuel-sodium reaction product and its influence on breached mixed-oxide fuel pins10.1016/0022-3115(93)90224-M ↗
36. Key differences in the fabrication, irradiation and high temperature accident testing of US and German TRISO-coated particle fuel, and their implications on fuel performance10.1016/S0029-5493(03)00033-5 ↗
37. Hanson · 2004
38. Assessment of different materials for meeting the requirement of future fuel designs
39. U3Si2 behavior in H2O: Part I, flowing steam and the effect of hydrogen10.1016/j.jnucmat.2018.01.002 ↗
40. U3Si2 behavior in H2O environments: Part II, pressurized water with controlled redox chemistry10.1016/j.jnucmat.2017.12.026 ↗
41. Coupled thermochemical, isotopic evolution and heat transfer simulations in highly irradiated UO2 nuclear fuel10.1016/j.jnucmat.2013.05.060 ↗
42. Silicon carbide corrosion in high-temperature gas-cooled reactor fuel particles10.13182/NT77-A31902 ↗
43. Pearson · 1979
44. Kittel · 1958
45. Factors affecting the anisotropy of irradiation creep and growth of zirconium alloys10.1016/0001-6160(79)90201-3 ↗
46. Greenwood · 1985
47. Designing radiation resistance in materials for fusion energy10.1146/annurev-matsci-070813-113627 ↗
48. Comparison of swelling and irradiation creep behavior of fcc-austenitic and bcc-ferritic/martensitic alloys at high neutron exposure10.1016/S0022-3115(99)00225-1 ↗
49. Observation and possible mechanism of irradiation induced creep in ceramics10.1016/j.jnucmat.2012.11.035 ↗
50. Improving atomic displacement and replacement calculations with physically realistic damage models10.1038/s41467-018-03415-5 ↗
51. Primary radiation damage: a review of current understanding and models10.1016/j.jnucmat.2018.10.027 ↗
52. Mathematical modeling and analysis of fuel rods10.1016/0029-5493(74)90095-8 ↗
53. Light water reactor fuel performance modeling and multi-dimensional simulation
54. Mechanistic materials modeling for nuclear fuel performance10.1016/j.anucene.2017.03.005 ↗
55. Stanek · 2019
56. Multidimensional multiphysics simulation of nuclear fuel behavior10.1016/j.jnucmat.2012.01.012 ↗
57. Swiler · 2017
58. Uncertainty and sensitivity analysis of fission gas behavior in engineering-scale fuel modeling10.1016/j.jnucmat.2014.09.077 ↗
59. U and Xe transport in UO 2±x: density functional theory calculations10.1103/PhysRevB.84.054105 ↗
60. Determination of krypton diffusion coefficients in uranium dioxide using atomic scale calculations10.1021/acs.inorgchem.6b01560 ↗
61. Cluster dynamics simulation of uranium self-diffusion during irradiation in UO2
62. Mechanical properties of neutron-irradiated nickel-containing martensitic steels: II. Review and analysis of helium-effects studies10.1016/j.jnucmat.2006.05.049 ↗
63. Fracture toughness and Charpy impact properties of several RAFMS before and after irradiation in HFIR10.1016/j.jnucmat.2007.03.165 ↗
64. Stability of SiC and its composites at high neutron fluence10.1016/j.jnucmat.2010.12.088 ↗
65. Impact of neutron irradiation on mechanical performance of FeCrAl alloy laser-beam weldments10.1016/j.jnucmat.2018.03.036 ↗
66. Experimental design and analysis for irradiation of SiC/SiC composite tubes under a prototypic high heat flux10.1016/j.jnucmat.2017.04.058 ↗
67. High burnup rim project,(II) progress of irradiation and preliminary analysis
68. High burnup rim project:(III) properties of rim-structured fuel
69. Szőke · 2014
70. Tverberg · 2014
71. Wiesnack · 1996
72. Separate effects irradiation testing of miniature fuel specimens10.1016/j.jnucmat.2019.151783 ↗
73. A revised capsule design for the accelerated testing of advanced reactor fuels
74. Relationship between preferred orientation, thermal expansion, and radiation-induced length changes in graphite10.1063/1.1714373 ↗
75. Stored energy release in neutron irradiated silicon carbide10.1016/j.jnucmat.2018.12.005 ↗
76. Matpro - a library of materials properties for light-water-reactor accident analysis, SCDAP/RELAP5/MOD 3.3 code manual Vol.4
77. The U-ZrH x alloy: its properties and use in TRIGA fuel10.1016/0029-5493(81)90135-7 ↗
78. Material property correlations for uranium mononitride: I. physical properties10.1016/0022-3115(90)90374-V ↗
79. Material property correlations for uranium mononitride: II. mechanical properties10.1016/0022-3115(90)90375-W ↗
80. Material property correlations for uranium mononitride: III. Transport properties10.1016/0022-3115(90)90376-X ↗
81. Material property correlations for uranium mononitride: IV. Thermodynamic properties10.1016/0022-3115(90)90377-Y ↗
82. Handbook of SiC properties for fuel performance modeling10.1016/j.jnucmat.2007.05.016 ↗
83. Experimentally known properties of U-10Zr alloys: a critical review10.1080/00295450.2018.1435137 ↗
84. A critical review of the experimentally known properties of U-Pu-Zr alloys. Part 1: phases and phase diagrams10.1080/00295450.2019.1578573 ↗
85. A critical review of the experimentally known properties of U-Pu-Zr alloys. Part 2: thermal and mechanical properties
86. Field · 2018
87. Fuels for sodium-cooled fast reactors: US perspective10.1016/j.jnucmat.2007.05.010 ↗
88. Long time experience with the development of HTR fuel elements in Germany10.1016/S0029-5493(02)00128-0 ↗
89. Petti · 2017
90. Olander · 1976
91. Mahmood · 2018
92. Jensen · 2018
93. TREAT restart project
94. US announces plans to build fast-neutron source10.1088/2058-7058/32/9/15 ↗
95. The jules Horowitz reactor research project: a new high performance material testing reactor working as an international user facility–first developments to address R&D on material
96. Cluster dynamics simulation of uranium self-diffusion during irradiation in UO210.1016/j.jnucmat.2019.151787 ↗