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    Journals >High Power Laser and Particle Beams >Volume 34 >Issue 2 >Page 026008 > Article
    • High Power Laser and Particle Beams
    • Vol. 34, Issue 2, 026008 (2022)
    The validation and calculation of highly enriched uranium models in JMCT
    Bo Shi and Xiaobo Liu*
    Author Affiliations
  • China Academy of Engineering Physics, Institute of Nuclear Physics and Chemistry, Mianyang 621900, China
    • show less
    DOI: 10.11884/HPLPB202234.210352 Cite this Article
    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 Copy Citation Text show less
    Results of thermal model calculation
    Fig. 1. Results of thermal model calculation
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    Results of intermediate model calculattion
    Fig. 2. Results of intermediate model calculattion
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    Results of fast model calculation
    Fig. 3. Results of fast model calculation
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    Results of mixed model calculation
    Fig. 4. Results of mixed model calculation
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    thermalintermediatefastmixedtotal
    metal6517331
    compound632213
    solution820010
    miscellaneous20002
    total221019556
    Table 1. Categorization of the benchmarking models selected
    identifierdescriptionmajor fission nuclidesmajor nonfissionable nuclides
    HEU-MET-THERM-001stacking of square platesU235, U238Si, C, H, O
    HEU-MET-THERM-006lattices of square fuel elementsU235, U238H, O
    HEU-MET-THERM-007square arrangement of fuel elementsU235, U238Fe, Cr, H, O
    HEU-MET-THERM-009stacking of square platesU235, U238Mg, C, H, O
    HEU-MET-THERM-011rectangular basket with built-in fuel platesU235, U238H, O, Al
    HEU-MET-THERM-012stacking of square platesU235, U238C, H
    HEU-COMP-THERM-001square arrangement of fuel cansU235, U238C, H, O
    HEU-COMP-THERM-003arrangement of cross-shaped fuel rodU235, U238C, H, O, Cu
    HEU-COMP-THERM-005hexagonal arrangement of fuel clusterU235, U238C, H, O, Cu
    HEU-COMP-THERM-007arrangement of cross-shaped fuel rodU235, U238C, H, O, Zr, Cu
    HEU-COMP-THERM-010fuel-pin arrays in waterU235, U238H, O, Be
    HEU-COMP-THERM-012square arrangement of fuel rodsU235, U238H, O, Si
    HEU-SOL-THERM-001unreflected tanks filled with uranyl nitrateU235, U238H, O, N
    HEU-SOL-THERM-003plexiglas reflected tanks filled with uranyl nitrateU235H, O, N, C
    HEU-SOL-THERM-005cylindrical tank filled with fission solutionU235, U238H, O, N, B, Si
    HEU-SOL-THERM-007concrete-reflected arrays of tanks filled with fission solutionU235N, H, O, C, Al, Cr, Fe
    HEU-SOL-THERM-009sphere with a fuel regionU235H, O, F, Al
    HEU-SOL-THERM-011sphere with a fuel regionU235H, O, F, Al
    HEU-SOL-THERM-013sphere with a fuel regionU235, U238H, O, N, Al
    HEU-SOL-THERM-032sphere containing uranyl nitrateU235, U238H, O, N, Al
    HEU-MISC-THERM-001lattices of square fuel elementsU235, U238H, O, B, N
    HEU-MISC-THERM-002lattices of fuel pinsU235, U238B, N, O, H
    Table 2. Description of the thermal models
    identifierdescriptionmajor fission nuclidesmajor nonfissionable nuclides
    HEU-MET-INTER-001stacking of core fuel platesU235, U238Fe, Cr
    HEU-MET-INTER-002stacking of cylindrical platesU235, U238C, H, Ti
    HEU-MET-INTER-003stacking of cylinders with reflectorU235, U238Be, O
    HEU-MET-INTER-004stacking of cylinders with reflectorU235, U238C, H
    HEU-MET-INTER-008assemblies of cylindrical tubesU235, U238, Th232C, H, O, Al
    HEU-COMP-INTER-001complex cone configuration with fuelU235O, Be, H, Zr, W, Al
    HEU-COMP-INTER-003cylindrical arrangement of component partsU235, U238H, O, N, Be, C
    HEU-COMP-INTER-006hexagonal tank with fuel tubes in square reflector tankU235, U238O, H, C
    HEU-SOL-INTER-001four-region sphereU235H, O, F
    HEU-SOL-INTER-002three-region sphere with critical height fuel solutionU235, U238H, O, F, Fe, C
    Table 3. Description of the intermediate models
    identifierdescriptionmajor fission nuclidesmajor nonfissionable nuclides
    HEU-COMP-FAST-001fuel cans configured in rectangular-pitched arrayU235, U238C, H, O
    HEU-COMP-FAST-003hexagonal tank with fuel tubes in square reflector tankU235, U238O, C, H
    HEU-MET-FAST-001unreflected set of concentric spherical shellsU235, U238N, O
    HEU-MET-FAST-003tuballoy-reflected sphereU235, U238−
    HEU-MET-FAST-004sphere stands on the seatU235C, H, O
    HEU-MET-FAST-008part of symmetric spheresU235Fe, Cu
    HEU-MET-FAST-009part of symmetric spheresU235, U238Be, Fe, Cu
    HEU-MET-FAST-011sphere with two hemisphere shellU235, U238C, H
    HEU-MET-FAST-012part of symmetric spheresU235Al, Cu, Fe
    HEU-MET-FAST-013part of symmetric spheresU235, U238Cu, Fe
    HEU-MET-FAST-014part of symmetric spheresU235, U238Al, Fe
    HEU-MET-FAST-015two cylinder with axial holesU235, U238Fe
    HEU-MET-FAST-018hollow sphereU235, U238C, Fe
    HEU-MET-FAST-019hollow sphere with reflectorU235, U238C
    HEU-MET-FAST-020sphere with reflectorU235, U238C, H
    HEU-MET-FAST-021hollow sphere with reflectorsU235, U238C, Fe
    HEU-MET-FAST-022hollow sphere with reflectorU235, U238C, Al, Cu
    HEU-MET-FAST-026square arrangement of cylinders with reflectorsU235, U238C, H, Fe
    HEU-MET-FAST-028sphere with reflectorU235, U238−
    Table 4. Description of the fast models
    identifierdescriptionmajor fission nuclidesmajor nonfissionable nuclides
    HEU-MET-MIXED-001stacking of cylinders with reflectorU235, U238C, H, Ti, Fe
    HEU-MET-MIXED-003six-region sphereU235C, H
    HEU-MET-MIXED-006stacking of cylindersU235, U238C, H, Fe
    HEU-COMP-MIXED-001fuel cans configured in rectangular-pitched arrayU235C, Fe, H, O, C
    HEU-COMP-MIXED-003complex cone configuration with fuelU235O, Be, H, Zr, W, Al
    Table 5. Description of the mixed models
    relative deviation of keff
    averageminimummaximum
    JMCT results0.006 550.000 410.018 91
    MCNP results0.005 460.000 260.014 78
    Table 6. Statistical analysis of thermal model results
    relative deviation of keff
    averageminimummaximum
    JMCT results0.017 210.001 040.044 78
    MCNP results0.009 760.000 490.034 95
    Table 7. Statistical analysis of intermediate model results
    relative deviation of keff
    averageminimummaximum
    JMCT results0.003 220.000 080.012 00
    MCNP results0.004 300.000 000.026 19
    Table 8. Statistical analysis of fast model results
    relative deviation of keff
    averageminimummaximum
    JMCT results0.008 400.001 560.025 02
    MCNP results0.003 520.000 440.007 95
    Table 9. Statistical analysis of mixed model results
    Abstract
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    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
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