Preliminary Probabilistic Safety Assessment for SMART
Creators
- 1. Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)
- 2. Responsible Engineering Technology, Seoul (Korea, Republic of)
Description
The SMART(System-integrated Modular Advanced ReacTor) Pre-project Engineering joint project is performing with Korea and Kingdom of Saudi Arabia. As a part of this project, the preliminary PSA was performed. The SMART is the integral type of a pressurized water reactor with a nominal thermal power is 365 megawatt thermal power, which contains core, reactor coolant pumps, steam generators and pressurizer within a single reactor pressure vessel. The inner diameter of all pipes of the primary system less than 2 inches because of SMART design features, so the large break LOCA(Loss of Coolant Accident) could be eliminated. The active support system are designed as the RTNSS(Regulatory Treatment of Non Safety Systems) requirements to ensure their reliability. The PSA is performing to confirm the safety level and to find the vulnerability for SMART plant which is performing. In this paper, the results of preliminary level-1 internal events PSA at power operation are presented. The preliminary PSA for SMART was performed to confirm the safety and to find the vulnerability for SMART plant. Ten event trees were developed and quantification was performed for 10 initiating events category. The quantification results shows that no vulnerable point in SMART design but some detailed analysis is needed to reduce uncertainty and conservatism such as ATWS(Anticipated Transient Without SCRAM) and passive safety system reliability analysis.
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 Spring Meeting
- Imprint Pagination
- vp.
- Journal Page Range
- [3 p.]
Conference
- Title
- 2018 Spring Meeting of the KNS
- Dates
- 16-18 May 2018
- Place
- Jeju (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 50059503
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- ATWS; NATURAL CONVECTION; PRESSURE VESSELS; PROBABILITY; PWR TYPE REACTORS; REACTOR VESSELS; RELIABILITY; REPUBLIC OF KOREA; SAFETY; SAFETY ANALYSIS; SAUDI ARABIA
- Descriptors DEC
- ACCIDENTS; ARAB COUNTRIES; ASIA; CONTAINERS; CONVECTION; DEVELOPING COUNTRIES; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; HEAT TRANSFER; MASS TRANSFER; MIDDLE EAST; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 9 refs, 3 figs, 2 tabs