Development of a core protection calculator module for the NSSS transient analyzer based on best-estimate codes for light water reactors
Creators
- 1. FNC Company, Seoul (Korea, Republic of)
- 2. Korea Electric Power Research Institute, Taejon (Korea, Republic of)
- 3. KAERI, Taejon (Korea, Republic of)
- 4. Hanyang University, Seoul (Korea, Republic of)
Description
KEPRI and KAERI have jointly developed a CPC (Core Protection Calculator) module as a part of the development project for an NSSS transient analyzer based on the best-estimate system code, RETRAN. To develop the CPC module as an NSSS transient analyzer, a number of code modifications, such as simplifications of text based input and interface with main program using the shared memory technique, were made to satisfy the analyzer requirements. In this paper, the safety analysis is carried out to confirm the feasibility of the CPC module for the loss of forced reactor coolant event of Ulchin unit 3 and 4. The results of the analysis are compared with those mentioned in FSAR and it is concluded that the CPC module shows acceptable trends during transients of the event
Additional details
Publishing Information
- Publisher
- KNS
- Imprint Place
- Taejon (Korea, Republic of)
- Imprint Title
- Proceedings of the KNS spring meeting
- Imprint Pagination
- [CD-ROM]
- Journal Page Range
- [12 p.]
Conference
- Title
- 2004 spring meeting of the KNS
- Dates
- 27-28 May 2004
- Place
- Gyeongju (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 35100434
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- FEASIBILITY STUDIES; R CODES; SAFETY ANALYSIS; STEAM SYSTEMS; TRANSIENTS; ULCHIN-3 REACTOR; ULCHIN-4 REACTOR; WATER COOLED REACTORS
- Descriptors DEC
- COMPUTER CODES; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; POWER REACTORS; PWR TYPE REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 7 refs, 6 figs, 3 tabs