Development of a fine and ultra-fine group cell calculation code slarom-uf for fast reactor analyses

Journal of Nuclear Science and Technology

Volumn 43, Issue 8, 2006, Pages 908-918

  Hazama, Taira ^a   Chiba, Go ^a   Sugino, Kazuteru ^a  

^a JAPAN ATOMIC ENERGY AGENCY   (Japan)

Author keywords

Cell calculation; Fast reactor; Fine group; JFS; JOYO; PEACO; Ultra fine group; ZPPR 10A

Indexed keywords

CELLS; MONTE CARLO METHODS; NUCLEAR ENERGY; RESONANCE;

CELL CALCULATION; FAST REACTOR; FINE GROUP; JFS; JOYO; PEACO; ULTRA-FINE GROUP; ZPPR-10A;

NUCLEAR REACTORS;

EID: 33748323132     PISSN: 00223131     EISSN: None     Source Type: Journal    
DOI: 10.1080/18811248.2006.9711176     Document Type: Article

References (29)

1. S. Katsuragi, T. Tone, A. Hasegawa, JAERI Fast Reactor Group Constants Systems Part I, JAERI 1195, (1970).
2. H. Takano, Y. Ishiguro, Production and Benchmark Tests of Fast Reactor Group Constant Set JFS-3-J2, JAERI-M 82135, (1978).
3. H. Noda, “Current status of fast reactor cycle system in Japan,” Proc. ICONE 8, Baltimore, USA, (2000).
4. T. Tone, “A numerical study of heterogeneity effects in fast reactor critical assemblies,” J. Nucl. Sci. Technol., 12[8], 467 (1975).
5. M. Nakagawa, “Double heterogeneity effect of fuel pin and subassembly in a fast power reactor,” Nucl. Sci. Eng., 83, 214 (1983).
6. M. Nakagawa, M. Katsuragi, H. Narita, ESELEM 4: A Code for Calculatng Fine Neutron Spectrum and Multi-Group Cross Sections in Plate Lattice, JAERI 1245, (1976).
7. S. Iijima, H. Shukuya, et al., Fine Energy Group Cell Calculation Code SP-2000 and Analysis ofZPPR-9 and ZPPR-13A Experiments, JAERI-m 59-115, (1984).
8. Y. Ishiguro, H. Takano, PEACO: A Code for Calculation of Group Constant of Resonance Energy Region in Heterogeneous Systems, JAERI 1219, (1971).
9. S. Okajima, H. Oigawa, T. Mukaiyama, “Resonance interaction effect between hot sample and cold core in analysis of doppler effect measurement,” J. Nucl. Sci. Technol., 31[10], 1097 (1994).
10. P. H. Kier, A. A. Robba, RABBLE, A Program for Computation of Resonance Absorption in Multiregion Reactor Cells, ANL-7326, (1967).
11. K. Tsuchihashi, H. Takano, et al., SRAC: JAERI Thermal Reactor Standard Code System for Reactor Design and Analysis, JAERI 1285, (1983).
12. K. Tsujimoto, T. Sasa, et al., “Neutronics design for lead-bis-muth cooled accelerator-driven system for transmutation of minor actinide,” J. Nucl. Sci. Technol., 41[1], 21 (2004).
13. M. Nakagawa, K. Tsuchihashi, SLAROM: A Code for Cell Homogenization calculation of Fast Reactor, JAERI 1294, (1984).
14. T. Nakagawa, et al., “Japanese Evaluated Nuclear Data Library Version 3 Revision-2: JENDL-3.2,” J. Nucl. Sci. Technol., 32[12], 1259 (1995).
15. K. Shibata, et al., “Japanese Evaluated Nuclear Data Library Version 3 Revision-3: JENDL-3.3,” J. Nucl. Sci. Technol., 39[11], 1125 (2002).
16. R. W. Roussin, VITAMIN-E: A Coupled 174-Neutron, 38-Gamma-Ray Multigroup Cross-section library for Deriving Application-Dependent Working Libraries for Radiation Transport Calculations, DLC-113, Oak Ridge National Laboratory, (1984).
17. R. E. MacFarlane, D. W. Muir, The NJOYNuclear Data Processing System, version 91, LA-12740-M, (1994).
18. D. E. Cullen, Program LINEAR (version 79-1): Linearized Data in the Evaluated Nuclear Data File/Version B (ENDF/B) Format, UCRL-50400, Vol. 17, Part A, (1979).
19. E. Cullen, Program RECENT (version 79-1): Reconstruction of Eenergy-Dependent Neutron Cross Sections from Resonance Parameters in the ENDF/B Format, UCRL-50400, Vol. 17, Part C, (1979).
20. E. Cullen, Program SIGMA1 (version 79-1): Doppler Broaden Evaluated Cross Sections in the Evaluated Nuclear Data File/Version B (ENDF/B) Format, UCRL-50400, Vol. 17, Part B, Rev. 2, (1979).
21. H. Takano, et al., TIMS-1:A processing Code for Production of Group Constants of Heavy Resonant Nuclei, JAERI 1267, (1980).
22. G. Chiba, “Criticality analyses for fast neutron systems sensitive to iron,” Trans. At. Energy Soc. Jpn., 4[1], 66 (2005).
23. K. Okumura, et al., SRAC95: General Purpose Neutronics Code System, JAERI/Data/Code 96-015, (1996), [in Japanese].
24. K. Yokoyama, et al., Reevaluation of Experimental Data and Analysis with the Latest Reactor Physics Calculatin Method on Fast Experimental Reactor “JOYO” MK-I Performance Tests, JNC TN9400 2005-024, (2005), [in Japanese].
25. M. Ishikawa, et al., Development of a Standard Data Base for FBR Core Nuclear Design (VIII); Complilation of JUPITER Analytical Results, JNC TN9410 97-099, (1997), [in Japanese].
26. K. Sugino, T. Iwai, Advances in Methods of Commercial FBR Core Characteristics Analyses; Investigations of a Treatment of the Double-heterogeneity and a Method to Calculate Homogenized Control Rod Cross Sections, JNC TN9410 98-067, (1998), [in Japanese].
27. Y. Nakagawa, et al., MVP/GMVP II: General Purpose Monte Carlo Codes for Neutron and Photon Transport Calculations based on Continuous Energy and Multigroup Methods, JAERI 1348, (2005).
28. P. F. Rose, C. L. Dunford, Eds., ENDF-102, Data Formats and Procedures for the Evaluated Nuclear Data File, ENDF-6, BNL-NCS-44945, (1990).
29. T. Hazama, et al., “Verification of a nuclear analysis system for fast reactors using BFS-62 critical experiment,” J. Nucl. Sci. Technol., 41[12], 1259 (2004).