Indirect-cycle FBR cooled by supercritical steam-concept and design

Conference · Fri Jan 01 04:00:00 EST 1993 · Transactions of the American Nuclear Society; (United States)

OSTI ID:5885508

Yoshiaki, Oka; Tatjana, Jevremovic; Sei-ichi, Koshizuka ^[1]

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1. Univ. of Tokyo, Bunkyo (Japan)

Neutronic and thermal-hydraulic design of an in direct-cycle supercritical steam-cooled fast breeder reactor (SCFBR-I) is carried out to find a way to make low-cost FBRs (Ref. 1). The advantages of supercritical steam cooling are high thermal efficiency, low pumping power, simplified system (no primary steam generators and no Loeffler boilers), and the use of experienced technology in fossil-fired power plants. The design goals are fissile fuel breeding (compound system doubling time below 30 yr), 1000-M(electric) class out-put, high fuel discharge burnup, and a long refueling period. The coolant void reactivity should be negative throughout fuel lifetime because the loss-of-coolant accident is the design-basis accident. These goals have never been satisfied simultaneously in previous SCFBRs.

• OSTI ID: 5885508
• Report Number(s): CONF-930601--
• Conference Information: Journal Name: Transactions of the American Nuclear Society; (United States) Journal Volume: 68
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500* -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220100 -- Nuclear Reactor Technology-- Theory & Calculation
42 ENGINEERING
420400 -- Engineering-- Heat Transfer & Fluid Flow
ACCIDENTS
BREEDER REACTORS
BURNUP
COMPUTERIZED SIMULATION
COOLING
EFFICIENCY
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLUID FLOW
LOSS OF COOLANT
REACTIVITY
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CORES
REACTORS
SIMULATION
THERMAL ANALYSIS
THERMAL EFFICIENCY
TURBULENT FLOW