Published 2006 | Version v1
Book

Static Thermal Design Analyses of Supercritical Water-Cooled Fast Reactor

  • 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)

Part of:
Validation of the TRACE Code Against Post-Dryout Experiments in Tubes and Annuli

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.