Molten Salt Reactor Characteristics Involving Fuel Salt Flow and Temperature Distribution in the Steady State

Transactions of the Atomic Energy Society of Japan

Volumn 2, Issue 4, 2003, Pages 400-407

  Mitachi, Koshi ^a   Yamamoto, Takahisa ^a   Suzuki, Takashi ^a   Okijmura, Yoshihide ^a  

^a TOYOHASHI UNIVERSITY OF TECHNOLOGY   (Japan)

Author keywords

Delayed neutron precursor; Fuel salt How; Molten salt reactor; Neutron flux; Numerical analysis; Steady state characteristics

Indexed keywords

EID: 84885272150     PISSN: 13472879     EISSN: 21862931     Source Type: Journal    
DOI: 10.3327/taesj2002.2.400     Document Type: Article

References (4)

1. R. C. Robertson, et al., Conceptual Design Study of a SingleFluid Molten-Salt Breeder Reactor, ORNL-4541, (1970).
2. K. Mitachi, etal., IAEA-TECDOC-840, p. 183–193 (1995).
3. W. H. Sides, Control Studies of a 1000 MWe MSBR, ORNL-TM-2927, (1970).
4. Y. Shimazu, et al., “Nuclear safety analysis of a molten salt breeder reactor,” J. Nucl. Sci. Technol., 15[7], 514~522 (1978).