Published 2010 | Version v1
Miscellaneous

Fuel safety analysis following feeder break accident for refurbished Wolsong 1

  • 1. Korea Atomic Energy Research Inst., Yuseong-gu, Daejeon (Korea, Republic of)

Description

The objective of the fuel analysis for the postulated accident was to estimate the quantity and timing of a fission product release from fuels when a postulated single channel accident occurs in CANDU 6 reactors. In this study, a fuel safety analysis for the refurbished Wolsong 1 was carried out by using the latest IST (Industrial Standard Toolset) fuel code. The relevant accident scenario focused in this study was a feeder stagnation break accident. The amount of fission product inventory and its distribution during the normal operating conditions were calculated by using the latest ELESTRES-IST code. For a calculation of transient fission product release following the feeder stagnation break, it was assumed that all fuel sheaths in the channel were failed and the entire gap inventory was released instantaneously at the beginning of the accident. The additional releases from the grain boundary and in-grain bound inventories were estimated by applying the Gehl's release model. (author)

Part of:
Flexible fuel for the future. 11th international conference on CANDU fuel

Additional details

Publishing Information

Publisher
Canadian Nuclear Society
Imprint Place
Toronto, Ontario (Canada)
Imprint Title
Flexible fuel for the future. 11th international conference on CANDU fuel
Imprint Pagination
60.9 Megabytes
Journal Page Range
[12 p.]

Conference

Title
11. International conference on CANDU fuel
Dates
17-20 Oct 2010
Place
Niagara Falls, Ontario (Canada)

INIS

Country of Publication
Canada
Country of Input or Organization
Canada
INIS RN
47028622
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
CANDU TYPE REACTORS; FISSION PRODUCT RELEASE; REACTOR ACCIDENT SIMULATION; SAFETY ANALYSIS; WOLSUNG-1 REACTOR
Descriptors DEC
CANDU TYPE REACTORS; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; NATURAL URANIUM REACTORS; PHWR TYPE REACTORS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTORS; SIMULATION; THERMAL REACTORS

Optional Information

Notes
7 refs., 7 tabs., 2 figs.