BibTeX

@inproceedings{DenmanPSA2013,
title = {Discrete Dynamic Event Tree Analysis of Small Modular Reactor Severe Accident Management},
author = {Matthew R Denman and Jeffrey Cardoni and Huafei Liao and Timothy Wheeler and Katrina M Groth},
year = {2013},
date = {2013-09-01},
booktitle = {Proceedings of PSA 2013 – the ANS International Topical Meeting on Probabilistic Safety Assessment and Analysis},
address = {Columbia, SC},
organization = {American Nuclear Society},
abstract = {Sandia National Laboratories conducted a proof-of-concept study to demonstrate the capability of existing severe accident analysis codes with branching and scheduling codes to implement a Discrete Dynamic Event Tree assessment of nuclear power plant accident response. This capability assessment was conducted on a generic iPWR plant model, using the MELCOR code for the plant simulator and ADAPT for the branching and scheduling code. The iPWR Capability Assessment served four primary functions:
1.Develop a stable dynamic MELCOR model,
2.Demonstrate the degree of stability for ADAPT/MELCOR simulations,
3.Develop DDET post processing methodologies for in depth DDET analysis, and
4.Provide insight into potential human intervention for a range of accident sequences.
The Capability Assessment study accomplished each of these functions. The Capability Assessment also allowed for the selection of important I&C variables which the operators would likely consult to assist in their accident mitigation decisions.},
keywords = {Bayesian Networks, Dynamic PRA, nuclear power, Probabilistic risk assessment (PRA), risk-informed procedures},
pubstate = {published},
tppubtype = {inproceedings}
}

Abstract

Sandia National Laboratories conducted a proof-of-concept study to demonstrate the capability of existing severe accident analysis codes with branching and scheduling codes to implement a Discrete Dynamic Event Tree assessment of nuclear power plant accident response. This capability assessment was conducted on a generic iPWR plant model, using the MELCOR code for the plant simulator and ADAPT for the branching and scheduling code. The iPWR Capability Assessment served four primary functions:
1.Develop a stable dynamic MELCOR model,
2.Demonstrate the degree of stability for ADAPT/MELCOR simulations,
3.Develop DDET post processing methodologies for in depth DDET analysis, and
4.Provide insight into potential human intervention for a range of accident sequences.
The Capability Assessment study accomplished each of these functions. The Capability Assessment also allowed for the selection of important I&C variables which the operators would likely consult to assist in their accident mitigation decisions.