Published 2011 | Version v1
Miscellaneous Metadata-only

Japanese SCWR fuel and core design study

Creators

  • 1. Toshiba Corp., Kanagawa (Japan)
  • 2. Univ. of Tokyo, Tokyo (Japan)
  • 3. Hitachi Ltd., Ibaraki (Japan)

Description

A study on design of fuel and core for a Japanese Supercritical Water-cooled reactor (JSCWR) was carried out The SCWR core and fuel characteristics have been studied with a 3D core simulator which is based on a 3D BWR core simulator, because SCWR core characteristics strongly depend on fuel loading pattern and control rod patterns. Maximum cladding surface temperature (MCST) has been evaluated by a subchannel analysis code, because MCST depends on coolant flow distribution and local power distribution in a fuel assembly. The fuel assembly concept that is suitable for the JSCWR is developed. A radial enrichment distribution, an axial enrichment zoning in the fuel assembly, a fuel loading pattern and an orifice pattern that satisfy the core design criteria and its MCST targets were studied. Other characteristics (maximum linear heat generation rate, shutdown margin, etc.) and MCST were also studied. Engineering uncertainties were considered for the evaluation of MCST. It was shown that the highest MCST satisfied the design target with 99.99% probability and 95% confidence limits. (author)

Additional details

Publishing Information

Publisher
Canadian Nuclear Society
Imprint Place
Toronto, Ontario (Canada)
ISBN
978-1-926773-02-5
Imprint Title
ISSCWR-5. The 5th International Symposium on Supercritical-Water-Cooled Reactors
Imprint Pagination
90.1 Megabytes
Journal Page Range
[12 p.]

Conference

Title
5. International Symposium on Supercritical-Water-Cooled Reactors
Dates
13-16 Mar 2011
Place
Vancouver, BC (Canada)

INIS

Country of Publication
Canada
Country of Input or Organization
Canada
INIS RN
48068373
Subject category
SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Quality check status
Yes
Descriptors DEI
COMPUTERIZED SIMULATION; JAPAN; NUCLEAR FUELS; PWR TYPE REACTORS; REACTOR CORES; THREE-DIMENSIONAL CALCULATIONS; TURBULENT FLOW; WATER COOLED REACTORS;
Descriptors DEC
ASIA; DEVELOPED COUNTRIES; ENERGY SOURCES; ENRICHED URANIUM REACTORS; FLUID FLOW; FUELS; MATERIALS; POWER REACTORS; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS;

Optional Information

Lead record
25k6d-wfc88
Notes
11 refs., 3 tabs., 15 figs.