Steady state analysis of small Molten Salt Reactor (effect of fuel salt flow on reactor characteristics)

JSME International Journal, Series B: Fluids and Thermal Engineering

Volumn 48, Issue 3, 2006, Pages 610-617

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

^a TOYOHASHI UNIVERSITY OF TECHNOLOGY   (Japan)

Author keywords

Delayed neutron precursor; Fuel salt flow; Molten Salt Reactor; Neutron flux

Indexed keywords

COMPUTER SIMULATION; FISSION REACTIONS; FLOW OF FLUIDS; MATHEMATICAL MODELS; MOLTEN MATERIALS; SALTS;

DELAYED NEUTRON PRECURSOR; FUEL SALT FLOW; MOLTEN SALT REACTOR; NEUTRON FLUX;

NUCLEAR REACTORS;

COMPUTER SIMULATION; FISSION REACTIONS; FLOW OF FLUIDS; MATHEMATICAL MODELS; MOLTEN MATERIALS; NUCLEAR REACTORS; SALTS;

EID: 33344457184     PISSN: 13408054     EISSN: None     Source Type: Journal    
DOI: 10.1299/jsmeb.48.610     Document Type: Article

References (13)

1. Robertson, R.C., Conceptual Design Study of a Single-Fluid Molten Salt Breeder Reactor (ORNL-4541), Oak Ridge National Laboratory, (1970).
2. Research Committee of Molten Salt Breeder Reactor, Molten Salt Breeder Reactor, Atomic Energy Society of Japan, Tokyo, (1977).
3. Mitachi, K., Furukawa, K. and Minami, K., Nuclear Characteristics of Small Molten Salt Reactor, (in Japanese), Atomic Energy Society of Japan, Vol.32 (1990), pp.377-384.
4. Mitachi, K., Furukawa, K., Yamana, Y. and Suzuki, T., Neutronic Examination on Plutonium Transmutation by a Small Molten Salt Reactor, IAEA-TECDOC-840, (1995), pp.183-195.
5. Sides, W.H., Control Studies of 1 000 MWe MSBR (ORNL-TM-2927), Oak Ridge National Laboratory, (1970).
6. Shimazu, Y., Nuclear Safety Analysis of a Molten Salt Breeder Reactor, Journal of Nuclear Science and Technology, Vol.15 (1978), pp.514-522.
7. Gonda, S., Mitachi, K., Yamamoto, T., Shimazu, Y. and Suzuki, S., A Study on the Characteristics of Small Molten Salt Reactor, (in Japanese), JSME Tokai Research Meeting, JSME Eds., Vol.2 (2002), pp.127-128.
8. Mitachi, K., Yamamoto, T., Gonda, S., Suzuki, T. and Okumura, Y., Reactor Characteristics of Molten Salt Reactor: An Approach of Solution Considering the Effect of Fuel Salt Flow, (in Japanese), Journal of Atomic Energy Society of Japan, Vol.2 (2003), pp.37-46.
9. Lamarsh, J.R., Introduction to Nuclear Engineering, (1975), Wesley, NY.
10. Okumura, K., SRAC: The Comprehensive Neutronics Calculation Code System (JAERI-Data/Code 96-015), Japan Atomic Energy Research Institute, (1996).
11. Yamamoto, K. and Ishimori, T., Summary of Nuclear Engineering, (1997), Baifukan, Tokyo.
12. JSME, JSME Data Book: Heat Transfer, 3rd Edition, (1978), JSME, Tokyo.
13. Patankar, S.V., Numerical Heat Transfer and Fluid Flow, (1980), MacGraw-Hill, NY.