Evaluation of the Integrity of Containment Pressure Boundary at Wolsong Unit 1 during a LOCA
- 1. NESS, Daejeon (Korea, Republic of)
- 2. KHNP, Gyeongju (Korea, Republic of)
Description
As a result, it is confirmed that the minimum water level of S/F discharge room drops to 0.49 m at 1,200 seconds after the accident in the case of the steam discharge, therefore, the water seal of S/F discharge room is not broken with the accident. That means the water head of S/F discharge room endures the pressure changes in a LOCA. This study enables to build a methodology to analyze pressure boundaries realistically by using RELAP5 code, confirming the applicability of RELAP5 code in CANDU reactors. In conclusion, the water head in the S/F discharge room is higher than the induced pressure from the inside of the containment during a LOCA combined with the total loss of dousing spray at Wolsong unit 1, even in the case of pure steam discharge.
Additional details
Publishing Information
- Publisher
- KNS
- Imprint Place
- Daejeon (Korea, Republic of)
- Imprint Title
- Proceedings of the KNS 2017 Fall Meeting
- Imprint Pagination
- [1 CD-ROM]
- Journal Page Range
- [3 p.]
Conference
- Title
- 2017 Fall Meeting of the KNS
- Dates
- 25-27 Oct 2017
- Place
- Kyungju (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 49079005
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- CONTAINMENT; LOSS OF COOLANT; R CODES; SPENT FUEL STORAGE; STEAM; USES; WOLSUNG-1 REACTOR
- Descriptors DEC
- ACCIDENTS; CANDU TYPE REACTORS; COMPUTER CODES; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; NATURAL URANIUM REACTORS; PHWR TYPE REACTORS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR ACCIDENTS; REACTORS; STORAGE; THERMAL REACTORS
Optional Information
- Notes
- 4 refs, 5 figs, 2 tabs