Published 2014 | Version v1
Book

Development of Surrogate Model for Prediction of Corium Debris Agglomeration - 14366

  • 1. Division of Nuclear Power Safety, Royal Institute of Technology - KTH, Roslagstullsbacken 21, SE-106 91, Stockholm (Sweden)
  • 2. Electrogorsk Research and Engineering Center on Nuclear Power Plants Safety - Erec, Saint Constantine 6, 142530, Electrogorsk (Russian Federation)

Description

Ex-vessel severe accident mitigation strategy in Nordic type Boiling Water Reactors (BWRs) imply that melt released into a deep pool of water below reactor vessel will form a coolable by natural circulation porous debris bed. However, if liquid melt is not completely fragmented and quenched when it reaches the bottom of the pool it can cause agglomeration of debris, increasing hydraulic resistance and thus worsening coolability of the bed. In the previous work we have developed and validated an approach to prediction of mass fractions of agglomerated debris using Fuel-Coolant Interaction (FCI) code VAPEX-P. This paper discusses development of a surrogate model (SM) which can predict fraction of agglomerated debris with high computational efficiency. Such model is a must for affordable sensitivity and uncertainty analysis in different accident scenarios. Details of the SM development and verification against full model are provided in the paper. (authors)

Additional details

Publishing Information

Publisher
American Nuclear Society - ANS
Imprint Place
La Grange Park, IL (United States)
ISBN
978-0-89448-776-7
Imprint Pagination
10 p.

Conference

Title
International Congress on Advances in Nuclear Power Plants
Acronym
ICAPP 2014
Dates
6-9 Apr 2014
Place
Charlotte, NC (United States)

Optional Information

Notes
36 refs.; Available on CD-ROM from American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (US)