Prediction of Major Transient Scenarios for Severe Accidents of Nuclear Power Plants Using GMDH
- 1. Chosun University, Gwangju (Korea, Republic of)
Description
It is important for operators and technical staffs to find out what an initiating event of a severe accident is by observing initial short time trends of major parameters in order to effectively accomplish severe accident management strategies. If they know some time sequences of major severe accident scenarios, they can cope with situations that can lead to the worst situation that plant safety systems do not work appropriately. The present work aims to classify the initiating events which may lead to severe accident conditions such as loss of coolant accidents (LOCA) and steam generator tube rupture (SGTR) by applying a support vector classification (SVC). Also, another objective is to identify the major severe accident scenarios such as core uncovery, core exit temperature (CET) and reactor vessel (RV) failure by using a group method of data handling (GMDH) algorithm of which the inputs are the time-integrated values of important measured signals during a short time interval after reactor scram. The proposed algorithm for the initiating event classification and the major severe accident scenario identification is verified by comparison with the simulation data of the MAAP4 code for the advanced power reactor 1400 (APR1400) developed by Korea Hydro and Nuclear Power company (KHNP)
Additional details
Publishing Information
- Publisher
- KNS
- Imprint Place
- Daejeon (Korea, Republic of)
- Imprint Title
- Proceedings of the KNS autumn meeting
- Imprint Pagination
- [1 CD-ROM]
- Journal Page Range
- [2 p.]
Conference
- Title
- 2010 autumn meeting of the KNS
- Dates
- 21-22 Oct 2010
- Place
- Jeju (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 42085147
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- LOSS OF COOLANT; NUCLEAR POWER PLANTS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR VESSELS; SAFETY; STEAM GENERATORS; TRANSIENTS
- Descriptors DEC
- ACCIDENTS; BOILERS; CONTAINERS; ENRICHED URANIUM REACTORS; NUCLEAR FACILITIES; POWER PLANTS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; THERMAL POWER PLANTS; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 3 refs, 2 figs, 1 tab