High Power Laser and Particle Beams, Volume. 34, Issue 2, 026008(2022)
The validation and calculation of highly enriched uranium models in JMCT
Figures & Tables(13)
Table 1. Categorization of the benchmarking models selected
View tableView in ArticleTable 1. Categorization of the benchmarking models selected
thermal intermediate fast mixed total metal 6 5 17 3 31 compound 6 3 2 2 13 solution 8 2 0 0 10 miscellaneous 2 0 0 0 2 total 22 10 19 5 56
Table 2. Description of the thermal models
View tableView in ArticleTable 2. Description of the thermal models
identifier description major fission nuclides major nonfissionable nuclides HEU-MET-THERM-001 stacking of square plates U235, U238 Si, C, H, O HEU-MET-THERM-006 lattices of square fuel elements U235, U238 H, O HEU-MET-THERM-007 square arrangement of fuel elements U235, U238 Fe, Cr, H, O HEU-MET-THERM-009 stacking of square plates U235, U238 Mg, C, H, O HEU-MET-THERM-011 rectangular basket with built-in fuel plates U235, U238 H, O, Al HEU-MET-THERM-012 stacking of square plates U235, U238 C, H HEU-COMP-THERM-001 square arrangement of fuel cans U235, U238 C, H, O HEU-COMP-THERM-003 arrangement of cross-shaped fuel rod U235, U238 C, H, O, Cu HEU-COMP-THERM-005 hexagonal arrangement of fuel cluster U235, U238 C, H, O, Cu HEU-COMP-THERM-007 arrangement of cross-shaped fuel rod U235, U238 C, H, O, Zr, Cu HEU-COMP-THERM-010 fuel-pin arrays in water U235, U238 H, O, Be HEU-COMP-THERM-012 square arrangement of fuel rods U235, U238 H, O, Si HEU-SOL-THERM-001 unreflected tanks filled with uranyl nitrate U235, U238 H, O, N HEU-SOL-THERM-003 plexiglas reflected tanks filled with uranyl nitrate U235 H, O, N, C HEU-SOL-THERM-005 cylindrical tank filled with fission solution U235, U238 H, O, N, B, Si HEU-SOL-THERM-007 concrete-reflected arrays of tanks filled with fission solution U235 N, H, O, C, Al, Cr, Fe HEU-SOL-THERM-009 sphere with a fuel region U235 H, O, F, Al HEU-SOL-THERM-011 sphere with a fuel region U235 H, O, F, Al HEU-SOL-THERM-013 sphere with a fuel region U235, U238 H, O, N, Al HEU-SOL-THERM-032 sphere containing uranyl nitrate U235, U238 H, O, N, Al HEU-MISC-THERM-001 lattices of square fuel elements U235, U238 H, O, B, N HEU-MISC-THERM-002 lattices of fuel pins U235, U238 B, N, O, H
Table 3. Description of the intermediate models
View tableView in ArticleTable 3. Description of the intermediate models
identifier description major fission nuclides major nonfissionable nuclides HEU-MET-INTER-001 stacking of core fuel plates U235, U238 Fe, Cr HEU-MET-INTER-002 stacking of cylindrical plates U235, U238 C, H, Ti HEU-MET-INTER-003 stacking of cylinders with reflector U235, U238 Be, O HEU-MET-INTER-004 stacking of cylinders with reflector U235, U238 C, H HEU-MET-INTER-008 assemblies of cylindrical tubes U235, U238, Th232 C, H, O, Al HEU-COMP-INTER-001 complex cone configuration with fuel U235 O, Be, H, Zr, W, Al HEU-COMP-INTER-003 cylindrical arrangement of component parts U235, U238 H, O, N, Be, C HEU-COMP-INTER-006 hexagonal tank with fuel tubes in square reflector tank U235, U238 O, H, C HEU-SOL-INTER-001 four-region sphere U235 H, O, F HEU-SOL-INTER-002 three-region sphere with critical height fuel solution U235, U238 H, O, F, Fe, C
Table 4. Description of the fast models
View tableView in ArticleTable 4. Description of the fast models
identifier description major fission nuclides major nonfissionable nuclides HEU-COMP-FAST-001 fuel cans configured in rectangular-pitched array U235, U238 C, H, O HEU-COMP-FAST-003 hexagonal tank with fuel tubes in square reflector tank U235, U238 O, C, H HEU-MET-FAST-001 unreflected set of concentric spherical shells U235, U238 N, O HEU-MET-FAST-003 tuballoy-reflected sphere U235, U238 − HEU-MET-FAST-004 sphere stands on the seat U235 C, H, O HEU-MET-FAST-008 part of symmetric spheres U235 Fe, Cu HEU-MET-FAST-009 part of symmetric spheres U235, U238 Be, Fe, Cu HEU-MET-FAST-011 sphere with two hemisphere shell U235, U238 C, H HEU-MET-FAST-012 part of symmetric spheres U235 Al, Cu, Fe HEU-MET-FAST-013 part of symmetric spheres U235, U238 Cu, Fe HEU-MET-FAST-014 part of symmetric spheres U235, U238 Al, Fe HEU-MET-FAST-015 two cylinder with axial holes U235, U238 Fe HEU-MET-FAST-018 hollow sphere U235, U238 C, Fe HEU-MET-FAST-019 hollow sphere with reflector U235, U238 C HEU-MET-FAST-020 sphere with reflector U235, U238 C, H HEU-MET-FAST-021 hollow sphere with reflectors U235, U238 C, Fe HEU-MET-FAST-022 hollow sphere with reflector U235, U238 C, Al, Cu HEU-MET-FAST-026 square arrangement of cylinders with reflectors U235, U238 C, H, Fe HEU-MET-FAST-028 sphere with reflector U235, U238 −
Table 5. Description of the mixed models
View tableView in ArticleTable 5. Description of the mixed models
identifier description major fission nuclides major nonfissionable nuclides HEU-MET-MIXED-001 stacking of cylinders with reflector U235, U238 C, H, Ti, Fe HEU-MET-MIXED-003 six-region sphere U235 C, H HEU-MET-MIXED-006 stacking of cylinders U235, U238 C, H, Fe HEU-COMP-MIXED-001 fuel cans configured in rectangular-pitched array U235 C, Fe, H, O, C HEU-COMP-MIXED-003 complex cone configuration with fuel U235 O, Be, H, Zr, W, Al
Table 6. Statistical analysis of thermal model results
View tableView in ArticleTable 6. Statistical analysis of thermal model results
relative deviation of keff average minimum maximum JMCT results 0.006 55 0.000 41 0.018 91 MCNP results 0.005 46 0.000 26 0.014 78
Table 7. Statistical analysis of intermediate model results
View tableView in ArticleTable 7. Statistical analysis of intermediate model results
relative deviation of keff average minimum maximum JMCT results 0.017 21 0.001 04 0.044 78 MCNP results 0.009 76 0.000 49 0.034 95
Table 8. Statistical analysis of fast model results
View tableView in ArticleTable 8. Statistical analysis of fast model results
relative deviation of keff average minimum maximum JMCT results 0.003 22 0.000 08 0.012 00 MCNP results 0.004 30 0.000 00 0.026 19
Table 9. Statistical analysis of mixed model results
View tableView in ArticleTable 9. Statistical analysis of mixed model results
relative deviation of keff average minimum maximum JMCT results 0.008 40 0.001 56 0.025 02 MCNP results 0.003 52 0.000 44 0.007 95
Tools
Get Citation
Copy Citation Text
Bo Shi, Xiaobo Liu. The validation and calculation of highly enriched uranium models in JMCT[J]. High Power Laser and Particle Beams, 2022, 34(2): 026008
Paper Information
Category: Monte Carlo Methods and Applications
Received: Aug. 13, 2021
Accepted: Nov. 2, 2021
Published Online: Jan. 26, 2022
The Author Email: Liu Xiaobo (13881190590@163.com)
© Copyright 2018-2021 | Chinese Laser Press.
All Rights Reserved 沪ICP备15018463号-20