Test Data for USEPR Severe Accident Code Validation.

Rempe, J. L.

Technical Information Center Oak Ridge Tennessee

关键词: Reactor accidents;    Computer codes;    Thermal hydraulics;    Heat transfer;    Validation;   

RP-ID  :  DE2008912446

学科分类：工程和技术（综合）

美国|英语

来源: National Technical Reports 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 and 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.