Fuel safety analysis following feeder break accident for refurbished Wolsong 1
Creators
- 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)
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.