Development of Coupled Interface System between the FADAS Code and a Source-term Evaluation Code XSOR for CANDU Reactors
Creators
- 1. ENESYS, Taejon (Korea, Republic of)
- 2. Korea Institute of Nuclear Safety, Taejon (Korea, Republic of)
Description
An accident prevention system is essential to the industrial security of nuclear industry. Thus, the more effective accident prevention system will be helpful to promote safety culture as well as to acquire public acceptance for nuclear power industry. The FADAS(Following Accident Dose Assessment System) which is a part of the Computerized Advisory System for a Radiological Emergency (CARE) system in KINS is used for the prevention against nuclear accident. In order to enhance the FADAS system more effective for CANDU reactors, it is necessary to develop the various accident scenarios and reliable database of source terms. This study introduces the construction of the coupled interface system between the FADAS and the source-term evaluation code aimed to improve the applicability of the CANDU Integrated Safety Analysis System (CISAS) for CANDU reactors
Additional details
Publishing Information
- Publisher
- KNS
- Imprint Place
- Taejon (Korea, Republic of)
- Imprint Title
- Proceedings of the KNS autumn meeting
- Imprint Pagination
- [1 CD-ROM]
- Journal Page Range
- [2 p.]
Conference
- Title
- 2006 autumn meeting of the KNS
- Dates
- 2-3 Nov 2006
- Place
- Kyongju (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 38049419
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- CANDU TYPE REACTORS; F CODES; INTERFACES; SAFETY ANALYSIS; SOURCE TERMS; X CODES
- Descriptors DEC
- COMPUTER CODES; HEAVY WATER MODERATED REACTORS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTORS; THERMAL REACTORS
Optional Information
- Notes
- 2 refs, 1 fig, 2 tabs