Static Thermal Design Analyses of Supercritical Water-Cooled Fast Reactor
Creators
- 1. Nuclear Professional School, Graduate School of Engineering, The University of Tokyo 2-22 Shirane Shrakata, Tokai-mura, Naka-gun, Ibaraki, 319-1106 (Japan)
- 2. Department of Nuclear Engineering and Management, School of Engineering, The University of Tokyo 7-3-1 Hongo, Bunkyo-ku, Tokyo 113-8656 (Japan)
Description
Subchannel analyses have been carried out for SWFR. PCST difference arising from sub-channel heterogeneity has been calculated by using the improved sub-channel analysis code STARS and that was evaluated to be about 18 deg. C. Several suggestions have been also made for reducing the PCST difference arising from channel heterogeneity. Effect of local power peaking on deflection of cladding surface temperature is explained with actual pin power distribution taken from core depletion calculation in this paper. Maximum cladding surface temperature at nominal condition is evaluated to be 645.3 deg. C over the cycle. Statistical thermal design uncertainty associated with PCST calculation is evaluated by Monte-Carlo sampling technique combined with sub-channel analysis code. Maximum design uncertainty of PCST is calculated to be 51 deg C and is in a good agreement with that from RTDP method. Influence of downward flow in seed region on system sensitivity is investigated by improved Monte-Carlo thermal design procedure. Static thermal design limit of MCST is 701 deg. C (650 deg. C for nominal + 51 deg. C) within 95/95 limit for SWFR. (authors)
Additional details
Publishing Information
- Publisher
- American Nuclear Society - ANS
- Imprint Place
- La Grange Park (United States)
- ISBN
- 0-89448-698-5
- Imprint Title
- Proceedings of the 2006 international congress on advances in nuclear power plants - ICAPP'06
- Imprint Pagination
- 2734 p.
- Journal Page Range
- p. 310-319
Conference
- Title
- 2006 International congress on advances in nuclear power plants - ICAPP'06
- Dates
- 4-8 Jun 2006
- Place
- Reno - Nevada (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 39042843
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CLADDING; DESIGN; FAST REACTORS; MONTE CARLO METHOD; POWER DISTRIBUTION; SAMPLING; SENSITIVITY; SURFACES; WATER
- Descriptors DEC
- CALCULATION METHODS; DEPOSITION; EPITHERMAL REACTORS; HYDROGEN COMPOUNDS; OXYGEN COMPOUNDS; REACTORS; SURFACE COATING
Optional Information
- Notes
- 11 refs.