Test Data for USEPR Severe Accident Code Validation

Rempe, J. L.

Idaho National Laboratory

关键词: Modeling;    Severe Accident Analysis Codes;    22 - General Studies Of Nuclear Reactors, 99 - General And Miscellaneous//Mathematics, Computing, And Information Science European Pressurized Reactor;    European Pressurized Reactor;   

DOI  :  10.2172/912446
RP-ID  :  INL/EXT-06-11326
RP-ID  :  DE-AC07-99ID-13727
RP-ID  :  912446

美国|英语

来源: UNT Digital Library

【 摘 要 】

This document identifies data that can be used for assessing various models embodied in severe accident analysis codes. Phenomena considered in this document, which were limited to those anticipated to be of interest in assessing severe accidents in the USEPR developed by AREVA, include: • Fuel Heatup and Melt Progression • Reactor Coolant System (RCS) Thermal Hydraulics • In-Vessel Molten Pool Formation and Heat Transfer • Fuel/Coolant Interactions during Relocation • Debris Heat Loads to the Vessel • Vessel Failure • Molten Core Concrete Interaction (MCCI) and Reactor Cavity Plug Failure • Melt Spreading and Coolability • Hydrogen Control Each section of this report discusses one phenomenon of interest to the USEPR. Within each section, an effort is made to describe the phenomenon and identify what data are available modeling it. As noted in this document, models in US accident analysis codes (MAAP, MELCOR, and SCDAP/RELAP5) differ. Where possible, this report identifies previous assessments that illustrate the impact of modeling differences on predicting various phenomena. Finally, recommendations regarding the status of data available for modeling USEPR severe accident phenomena are summarized.