Kinetic parameter βeff/ℓ measurement on low enriched uranyl nitrate solution with single unit cores (600훗;, 280T, 800훗;)of STACY

Journal of Nuclear Science and Technology

Volumn 39, Issue 11, 2002, Pages 1227-1236

  Tonoike, Kotaro ^a   Miyoshi, Yoshinori ^a   Kikuchi, Tsukasa ^b   Yamamoto, Toshihiro ^a  

^a JAPAN ATOMIC ENERGY AGENCY   (Japan)

^b TOSHIBA CORPORATION   (Japan)

Author keywords

CITATION; Effective delayed neutron fraction; Experimental data; JENDL; Kinetic parameter; Low enriched uranium; Prompt neutron lifetime; Pulsed neutron source method; SRAC; STACY; Uranyl nitrate solution

Indexed keywords

NEUTRON SOURCES; NUCLEAR FUELS; NUCLEAR REACTORS; REACTION KINETICS; SOLUTIONS;

KINETIC PARAMETERS;

URANIUM COMPOUNDS;

EID: 0036872784     PISSN: 00223131     EISSN: None     Source Type: Journal    
DOI: 10.1080/18811248.2002.9715315     Document Type: Article

References (11)

1. K. Tonoike, N. Izawa, S. Okazaki, et al., “New critical facilities toward their first criticality, STACY and TRACY in NUCEF,” Proc. 5th Int. Conf. On Nuclear Criticality Safety (ICNC), Albuquerque, USA, Sept. 17-21, 1995, Vol. 2, p. 10-25 (1995).
2. K. Tonoike, K. Nakajima, Y. Miyoshi, et al, “Review of the STACY & TRACY experiment programs since their first criticality,” Proc. 5th Int. Nucl. Conf on Recycling, Conditioning and Disposal (RECOD), Nice, France, Oct. 25-28, 1998, Vol. 1, p. 54(1998).
3. Y. Miyoshi, “Experimental program of STACY for criticality safety research on low enriched uranyl and plutonium nitrate solution,” Proc. 6th Int. Conf. On Nuclear Criticality Safety (ICNC), Versailles, France, Sept. 20-24, 1999, Vol. 2, p. 512 (1999).
4. Y. Miyoshi, T. Umano, K. Tonoike, et al., “Critical experiments on 10% enriched uranyl nitrate solution using a 60-cm-diameter cylindrical core,” Nucl. Technol., 118, 69 (1997).
5. T. Yamamoto, Y. Miyoshi, T. Kikuchi, et al., “Criticality safety benchmark experiment on 10% enriched uranyl nitrate solution sing a 28-cm-thickness slab core,” J. Nucl. Sci. Technol., 39[7], 789 (2002).
6. J. B. Briggs, V. F. Dean, L. Scott, et al., “History and status of the International Criticality Safety Benchmark Evaluation Project,” Trans. Am. Nucl. Soc., 78, 162 (1998).
7. S. R. Bierman, “Reactivity measurements under conditions typical to fuel element dissolution,” Nucl. Technol., 31, 339 (1976).
8. E. Garelis, J. L. Russell “Theory of pulsed neutron source measurements,” Nucl. Sci. Eng., 16, 263 (1963).
9. K. Okumura, K. Kaneko, K. Tsuchihashi, SRAC95: General Purpose Neutronics Code System, JAERI-Data/Code 96-015, Japan Atomic Energy Research Institute, (1996), [in Japanese].
10. T. Nakagawa, “Japanese Evaluated Nuclear Data Library Version-3 Revision-2: JENDL-3.2,” J. Nucl. Sci. Technol., 32, 1259(1995).
11. R. E. Alcouffe, R. S. Baker, F. W. Brinkley, et al., DANTSYS: A Diffusion Accelerated Neutral Particle Transport Code System, LA-12969-M, Los Alamos National Laboratory, (1995)