Design Study of Pb-Bi-Cooled and NaK-Cooled Small Reactors: PBWFR and DSFR

Conference · Thu Jul 01 00:00:00 EDT 2004

OSTI ID:21160595

Otsubo, Akira; Takahashi, Minoru ^[1]

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1. N1-18, Research Laboratory for Nuclear Reactors, Tokyo Institute of Technology, 2-12-1 O-okayama, Meguro-ku, Tokyo 152-8550 (Japan)

The liquid lead-bismuth eutectic (Pb-Bi) has good compatibility with water, which is different from sodium. It is expected that the Pb-Bi could be used as a coolant of the deep sea fast reactor (DSFR) and the Pb-Bi- cooled direct contact boiling water small fast reactor (PBWFR). Physics analysis of the Pb-Bi-cooled small reactor cores with and without inner control rods was performed using the computer program of General Purpose Neutronics Code System (SRAC95) developed by Japan Atomic Energy Research Institute (JAERI). The coolant of Pb-Bi seems to be good as well as NaK for small reactors. (authors)

• Research Organization: American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
• OSTI ID: 21160595
• Resource Relation: Conference: ICAPP'04: 2004 international congress on advances in nuclear power plants, Pittsburgh, PA (United States), 13-17 Jun 2004; Other Information: Country of input: France; Related Information: In: Proceedings of the 2004 international congress on advances in nuclear power plants - ICAPP'04, 2338 pages.
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BISMUTH
BOILING
COMPUTER CODES
CONTROL ELEMENTS
COOLANTS
DESIGN
FAST REACTORS
JAERI
LEAD
POTASSIUM ALLOYS
REACTOR CORES
SODIUM
SODIUM ALLOYS
WATER