Validating JENDL-3.3 for water-reflected low-enriched uranium solution systems using STACY ICSBEP benchmark models

Nuclear Science and Engineering

Volumn 145, Issue 1, 2003, Pages 132-144

  Yamamoto, Toshihiro ^a   Miyoshi, Yoshinori ^a   Kiyosumi, Takehide ^a  

^a JAPAN ATOMIC ENERGY AGENCY   (Japan)

Author keywords

[No Author keywords available]

Indexed keywords

ACCIDENT PREVENTION; BENCHMARKING; CALCULATIONS; COMPUTER SIMULATION; CRITICALITY (NUCLEAR FISSION); FISSION REACTIONS; HANDBOOKS; IRON; PERTURBATION TECHNIQUES; RADIOISOTOPES; URANIUM;

COMPUTER CODES; CRITICALITY SAFETY ANALYSIS; STATIC CRITICALITY EXPERIMENT FACILITY; WATER REFLECTED LOW ENRICHED URANIUM SOLUTION;

NUCLEAR REACTORS;

EID: 0042695594     PISSN: 00295639     EISSN: None     Source Type: Journal    
DOI: 10.13182/NSE03-A2369     Document Type: Article

References (17)

1. Y. Miyoshi, T. Umano, K. Tonoike, N. Izawa, S. Sugikawa, and S. Okazaki, "Critical Experiments on 10% Enriched Uranyl Nitrate Solution Using a 60-cm-Diameter Cylindrical Core," Nucl. Technol., 118, 69 (1997).
2. T. Yamamoto, Y. Miyoshi, T. Kikuchi, and S. Watanabe, "Criticality Safety Benchmark Experiment on 10% Enriched Uranyl Nitrate Solution Using a 28-cm-Thickness Slab Core," J. Nucl. Sci. Technol., 39, 7, 789 (2002).
3. Y. Yamane, Y. Miyoshi, S. Watanabe, and T. Yamamoto, "Critical Experiments on 10% Enriched Uranyl Nitrate Solution Using a 80-cm-Diameter Cylindrical Core," Nucl. Technol., 141, 221 (2003).
4. T. Yamamoto et al., "STACY: Water-Reflected 10%-Enriched Uranyl Nitrate Solution in a 60-cm-Diameter Cylindrical Tank," in "International Handbook of Evaluated Criticality Safety Benchmark Experiments," LEU-SOL-THERM-004, NEA/NSC/DOC(95)03, Organisation for Economic Cooperation and Development/Nuclear Energy Agency.
5. S. Watanabe et al., "STACY: 28-cm-Thick Slabs of 10% Enriched Uranyl Nitrate Solutions, Water-Reflected," in "International Handbook of Evaluated Criticality Safety Benchmark Experiments," LEU-SOL-THERM-016, NEA/NSC/DOC(95)03/IV, Organisation for Economic Co-operation and Development/Nuclear Energy Agency.
6. S. Watanabe et al., "STACY: 80-cm-Diameter Cylindrical Tank of 10% Enriched Uranyl Nitrate Solutions, Water-Reflected," in "International Handbook of Evaluated Criticality Safety Benchmark Experiments," LEU-SOL-THERM-020, NEA/NSC/DOC(95)03/IV, Organisation for Economic Cooperation and Development/Nuclear Energy Agency.
7. Y. Miyoshi et al., "Results of Criticality Safety Validation of Reprocessing Plant and Future Project of STACY," Proc. 5th Nuclear Fuel Cycle Safety Engineering Research Facility (NUCEF) Seminar, Tokai, Ibaraki, Japan, February 27, 2001, p. 34, JAERI-Conf 2001-015, Japan Atomic Energy Research Institute (2001) (in Japanese).
8. Y. Miyoshi, T. Yamamoto, and S. Watanabe, "Benchmark Evaluation on Single Core System Composed of 10% Enriched Uranyl Nitrate Solution at STACY," Proc. Int. Conf. Nuclear Data for Science and Technology, Tsukuba, Ibaraki, Japan, October 7-12, 2001, p. 971
9. Y. Miyoshi, T. Yamamoto, and S. Watanabe, "Benchmark Evaluation on Single Core System Composed of 10% Enriched Uranyl Nitrate Solution at STACY," J. Nucl. Sci. Technol., Suppl. 2 (2002).
10. H. Takano, T. Nakagawa, and K. Kaneko, "Validation of JENDL-3.3 by Criticality Benchmark Testing," Proc. Int. Conf. Nuclear Data for Science and Technology, Tsukuba, Ibaraki, Japan, October 7-12, 2001, p. 847
11. H. Takano, T. Nakagawa, and K. Kaneko, "Validation of JENDL-3.3 by Criticality Benchmark Testing," J. Nucl. Sci. Technol., Suppl. 2 (2002).
12. K. Shibata et al., "Japanese Evaluated Nuclear Data Library Version 3 Revision-3: JENDL-3.3," J. Nucl. Sci. Technol., 39, 11, 1125 (2002).
13. "MCNP-A General Monte Carlo N-Particle Transport Code, Version 4C," LA-13709-M, J. F. BRIESMEISTER, Ed., Los Alamos National Laboratory (2000). (2000).
14. T. Mori and M. Nakagawa, "MVP/GMVP: General Purpose Monte Carlo Codes," JAERI-Data/Code 94-007, Japan Atomic Energy Research Institute (1994) (in Japanese).
15. T. Yamamoto and Y. Miyoshi, "Mechanisms of Positive Temperature Reactivity Coefficients of Dilute Plutonium Solutions," Nucl. Sci. Eng., 142, 305 (2002).
16. K. Okumura, K. Kaneko, and K. Tsuchihashi, "SRAC95; General Purpose Neutronics Code System," JAERI-Data/Code 96-015, Japan Atomic Energy Research Institute (1996) (in Japanese).
17. R. E. Alcouffe et al., "DANTSYS: A Diffusion Accelerated Neutral Particle Transport Code System," LA-12969-M, Los Alamos National Laboratory (1995).