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

Conference · Fri Jan 01 00:00:00 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-; CODEN: TANSAO
• Journal Information: Transactions of the American Nuclear Society; (United States), Vol. 68; Conference: American Nuclear Society (ANS) annual meeting, San Diego, CA (United States), 20-24 Jun 1993; ISSN 0003-018X
• Country of Publication: United States
• Language: English

Related Subjects

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