Published September 2013 | Version v1
Report Open

Participation in EU SARNET2 Project for an Enhancement of Severe Accident Evaluation Capability in Domestic NPPs

Description

Main objectives of this study is to analyze experimental results to enhance the understandings of main severe accident issues, and support resolution of the underlying issues through a participation to the Severe Accident Consortium Project SARNET-2. KAERI has participated in the five WPs(Work Package), which are essential in resolving domestic severe accident issues and enhancing the evaluation capability of Level-2 PSA. The following results were obtained through the SARNET2 research activities. □ WP4-2 : Establishment of the ASTCE application framework through its application to the RPV lower head corium behavior analysis of the reference plant. □ WP6-4 : Confirmation of the effect of water on top of the melt on the cavity concrete ablation process through the CORQUENCH and MELCOR code analysis. □ WP7-1 : Confirmation of the effect of simulant material composition on cooling mechanism and solidification process of molten debris particles during FCI. □ WP7-2 : Benchmark blind/open calculations for code validation against the IRSN ENACCEF experiments and application of the established framework to the reference plant. □ WP8-3 : Application of the ISSAC code for the SGTR/CFV-related source term issue resolution of the reference plant and analysis of the PHEBUS FRT-3 ST benchmark problem using the MELCOR code, The technology secured through the present project as well as experimental data and relevant reports for each WP will be used in resolving the remaining severe accident issues of domestic NPPs(including operating and new/advanced reactors) and also in enhancing the domestic Level-2 PSA capability

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Additional details

Publishing Information

Imprint Pagination
243 p.
Report number
KAERI/RR--3632/2013

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
45093066
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Descriptors DEI
C CODES; CORIUM; I CODES; M CODES; NUCLEAR POWER PLANTS; PROBABILITY; REACTOR ACCIDENTS; SAFETY ANALYSIS; SOLIDIFICATION
Descriptors DEC
ACCIDENTS; COMPUTER CODES; NUCLEAR FACILITIES; PHASE TRANSFORMATIONS; POWER PLANTS; THERMAL POWER PLANTS

Optional Information

Notes
194 refs, 140 figs, 56 tabs