Performance Assessment of Passive Containment Cooling System Using MAAP5 Code in Pressurized Light Water Reactor
- 1. KEPCO E and C, Daejeon (Korea, Republic of)
Description
It provides long-term cooling capability without external power supply and human intervention. The heat resulting from accidents is transferred to the passive containment cooling tank (PCCT) located outside of containment via heat exchanger placed inside of containment. In this paper, we carried out a thermal-hydraulic performance assessment of PCCS applied to Zion-like 4-loop nuclear power plant, a representative pressurized light water reactor (PWR) by using MAAP5.05 beta version code. A new PCCS model has been being developed for MAAP5 code. The new model consists of containment gas side heat transfer model including condensation effect and natural circulation of two-phase flow in the tube-side of a heat exchanger. In the present study, the PCCS model is tested for Zion-like 4 loop PWR. The results show that the PCCS can remove the decay heat in the containment and prevent the containment failure. However, the decay heat in the containment building is not reduced significantly in the late phase of accident in case of without long-term management of the PCCT water tank. Therefore the detailed assessment of the long term heat removal capability of the PCCS should be performed is expected.
Additional details
Identifiers
- URL
- https://www.kns.org;
Publishing Information
- Publisher
- KNS
- Imprint Place
- Daejeon (Korea, Republic of)
- Imprint Title
- Proceedings of the KNS 2018 Fall Meeting
- Imprint Pagination
- vp.
- Journal Page Range
- [3 p.]
Conference
- Title
- 2018 Fall Meeting of the KNS
- Dates
- 24-26 Oct 2018
- Place
- Yeosu (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 50060508
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- AFTER-HEAT; CONTAINMENT SYSTEMS; COOLING SYSTEMS; DECAY; FAILURES; M CODES; PERFORMANCE; PWR TYPE REACTORS; REMOVAL; SAFETY; TANKS
- Descriptors DEC
- COMPUTER CODES; CONTAINERS; CONTAINMENT; ENERGY SYSTEMS; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 5 refs, 4 figs