Developing the Stress Test Gap Analysis Methodology for Nuclear Power Plants
Creators
- 1. Korea Hydro and Nuclear Power Central Research Institute, Daejeon (Korea, Republic of)
Description
Korea had demonstrated the safety of long-term operational nuclear power plants by implementing stress test such as Wolsong-1 & Kori-1 unit. It was decided to extend the stress test to all the nuclear power plants in Korea. And KHNP is evaluating the capability of responding to the operational plant in the event of severe accidents that exceed the design basis. The stress test will be conducted in the first stage; conduct a representative nuclear power plant test for each reactor type, OPR1000, CANDU, Framatom, Westinghouse types, included partial of APR1400. The public questioned the safety of nuclear power plant after the Fukushima accident. Korea has already proven the safety of nuclear power plant through conducting the stress test on the long-term operation. Now a new challenge has begun. It will prove all of the nuclear power plants in Korea. As noted earlier, it is very difficult to conduct a stress test on an entire plant in a short time. The stress test is also more complicated in Korea, where various types of nuclear reactors are mixed up. Under these difficult conditions, the methodology for the GAP analysis was developed for conducting the effective stress test.
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
- 50059533
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- ACCURACY; CANDU TYPE REACTORS; DESIGN; NUCLEAR POWER PLANTS; PWR TYPE REACTORS; SAFETY; STRESSES
- Descriptors DEC
- ENRICHED URANIUM REACTORS; HEAVY WATER MODERATED REACTORS; NUCLEAR FACILITIES; POWER PLANTS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTORS; THERMAL POWER PLANTS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 2 refs, 1 fig, 2 tabs