skip to main content

SciTech ConnectSciTech Connect

Title: RAVEN as Control Logic and Probabilistic Risk Assessment Driver for RELAP-7

The Next Generation of System Analysis Code (NGSAC) [1] aims to model and simulate the Nuclear Power Plant (NPP) thermo-hydraulic behavior with high level of accuracy. In this respect, Idaho National Laboratory (INL) is developing a NGSAC (known as RELAP-7) which will allow to model NPP responses for a set of accident scenarios (e.g., loss of off-site power).
Authors:
; ; ; ;
Publication Date:
OSTI Identifier:
1060968
Report Number(s):
INL/CON-12-26352
DOE Contract Number:
DE-AC07-05ID14517
Resource Type:
Conference
Resource Relation:
Conference: 2012 ANS Winter Meeting,San Diego, CA,11/11/2012,11/15/2012
Research Org:
Idaho National Laboratory (INL)
Sponsoring Org:
DOE - NE
Country of Publication:
United States
Language:
English
Subject:
99 GENERAL AND MISCELLANEOUS Dynamic PRA; Stochastic Systems; Uncertainty quantification