Minor actinide-bearing oxide fuel core design study for the JSFR

Nuclear Technology

Volumn 170, Issue 1, 2010, Pages 170-180

  Naganuma, Masayuki ^a   Ogawa, Takashi ^a   Ohki, Shigeo ^a   Mizuno, Tomoyasu ^a   Kotake, Shoji ^b  

^a JAPAN ATOMIC ENERGY AGENCY   (Japan)

^b Mitoshiro Bldg   (Japan)

Author keywords

Core design; Minor actinide bearing fuel; Sodium cooled fast reactor

Indexed keywords

FAST REACTORS; HEAVY METALS; LIGHT WATER REACTORS; RECYCLING; SODIUM; THERMAL CONDUCTIVITY OF GASES; WATER RECYCLING;

CORE DESIGN; FAST BREEDER REACTORS; LIGHT WATER REACTOR (LWR); MINOR ACTINIDE; SODIUM COOLED FAST REACTOR; SODIUM COOLED FAST REACTORS (SFR); SODIUM VOID REACTIVITY; TECHNOLOGY DEVELOPMENT;

FUELS;

EID: 77950997199     PISSN: 00295450     EISSN: None     Source Type: Journal    
DOI: 10.13182/NT10-A9455     Document Type: Article

References (14)

1. Y. SAGAYAMA, "Launch of Fast Reactor Cycle Technology Development Project in Japan," Proc. Global 2007, Boise, Idaho, September 9-13, 2007, p. 251, American Nuclear Society (2007) (CD-ROM).
2. H. NIWA, K. AOTO, and M. MORISHTTA, "Current Status and Perspective of Advanced Loop Type Fast Reactor in Fast Reactor Cycle Technology Development Project," Proc. Global 2007, Boise, Idaho, September 9-13, 2007, p. 62, American Nuclear Society (2007) (CD-ROM).
3. T. MIZUNO,T. OGAWA, M. NAGANUMA, andT.AIDA, "Advanced Oxide Fuel Core Design Study for SFR in the 'Feasibility Study' in Japan," Global 2005, Tsukuba, Japan, October 9-13, 2005.
4. T. MIZUNO and H. NIWA, "Advanced MOX Core Design Study of Sodium-Cooled Reactors in Current Feasibility Study on Commercialized Fast Reactor Cycle Systems in Japan," Nucl. Technol, 146, 155 (2004).
5. M. KONOMURA et al., "Feasibility Study on Commercialized Fast Reactor Cycle Systems Technical Study Report of Phase n-( 1) Fast Reactor Plant Systems," JAEA-Research 2006-2042, Japan Atomic Energy Agency (2006) (in Japanese).
6. S. UKAI et al., "Tube Manufacturing and Characterization of Oxide Dispersion Strengthened Ferritic Steels," J. Nucl. Mater., 283-287, 702 (2003).
7. T. KAITO, S. OHTSUKA, and M. INOUE, "Progress in the R&D Project on Oxide Dispersion Strengthened and Precipitation Hardened Ferritic Steels for Sodium Cooled Fast Breeder Reactor Fuels," Proc. Global 2007, Boise, Idaho, September 9-13, 2007, p. 37, American Nuclear Society (2007) (CD-ROM).
8. M. INOUE, T. KAITO, and S. OHTSUKA, "Research and Development of Oxide Dispersion Strengthened Ferritic Steels for Sodium Cooled Fast Breeder Reactor Fuels," Materials Issues for Generation IV Systems, p. 311, Springer (2008).
9. M. OGAWA et al., "Study on Reactor Core and Fuel Design of Sodium Cooled Fast Reactor (Mixed Oxide Fuel Core) Results in JFY2006," JAEA-Research 2007-084, Japan Atomic Energy Agency (2007) (in Japanese).
10. T. HAZAMA et al., "Development of the Unified CrossSection Set ADJ2000R for Fast Reactor Analysis," JNC TN9400 2002-2064, Japan Nuclear Cycle Development Institute (2002) (in Japanese).
11. T. OGAWA et al., "Study on Reactor Core and Fuel Design of Sodium Cooled Fast Reactor (Mixed Oxide Fuel Core) Results in JFY2005," JAEA-Research 2006-061, Japan Atomic Energy Agency (2006) (in Japanese).
12. S. OHKI and T. OGAWA, "A Design Study of SodiumCooled Core with MOX Fuel Containing MA (2) Development of the Core Concept Adopted to the TRU Recovered from LWR Spent Fuel," Proc. Atomic Energy Society of Japan 2007 Fall Mtg., Kitakyushu, Japan, September 27-29, 2007, p. D34, Atomic Energy Society of Japan (2007) (in Japanese).
13. M. KATO et al., "Evaluation of Thermal Physical Properties for Fast Reactor Fuels - Melting Point and Thermal Conductivities," JAEA-Technology 2006-049, Japan Atomic Energy Agency (2006) (in Japanese).
14. M. HISADA, S. KOYAMA, and K. YAMAMOTO, "Americium Redistribution in Americium Containing MOX Fuel (B8-HAM)," JNC TN9430 2000-2002, Japan Nuclear Cycle Development Institute (2000) (in Japanese).