Published May 2018 | Version v1
Miscellaneous

Developing the Stress Test Gap Analysis Methodology for Nuclear Power Plants

  • 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.

Part of:
Proceedings of the KNS 2018 Spring Meeting

Additional details

Identifiers

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