Indirect-cycle FBR cooled by supercritical steam-concept and design
- 1. Univ. of Tokyo, Bunkyo (Japan)
Description
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
Additional details
Publishing Information
- Journal Title
- Transactions of the American Nuclear Society
- Journal Volume
- 68
- Journal Page Range
- p. 448-449.
- ISSN
- 0003-018X
- CODEN
- TANSAO
Conference
- Title
- American Nuclear Society (ANS) annual meeting.
- Dates
- 20-24 Jun 1993.
- Place
- San Diego, CA (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 25022799
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S22: GENERAL STUDIES OF NUCLEAR REACTORS; S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BURNUP; COMPUTERIZED SIMULATION; COOLING; FBR TYPE REACTORS; LOSS OF COOLANT; REACTIVITY; REACTOR CORES; THERMAL ANALYSIS; THERMAL EFFICIENCY; TURBULENT FLOW
- Descriptors DEC
- ACCIDENTS; BREEDER REACTORS; EFFICIENCY; EPITHERMAL REACTORS; FAST REACTORS; FLUID FLOW; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; SIMULATION
Optional Information
- Secondary number(s)
- CONF-930601--.