BWR station blackout: A RISMC analysis using RAVEN and RELAP5-3D
- Idaho National Lab. (INL), Idaho Falls, ID (United States)
The existing fleet of nuclear power plants is in the process of extending its lifetime and increasing the power generated from these plants via power uprates and improved operations. In order to evaluate the impact of these factors on the safety of the plant, the Risk-Informed Safety Margin Characterization (RISMC) project aims to provide insights to decision makers through a series of simulations of the plant dynamics for different initial conditions and accident scenarios. This paper presents a case study in order to show the capabilities of the RISMC methodology to assess impact of power uprate of a Boiling Water Reactor system during a Station Black-Out accident scenario. We employ a system simulator code, RELAP5-3D, coupled with RAVEN which perform the stochastic analysis. Furthermore, our analysis is performed by: 1) sampling values from a set of parameters from the uncertainty space of interest, 2) simulating the system behavior for that specific set of parameter values and 3) analyzing the outcomes from the set of simulation runs.
- Research Organization:
- Idaho National Lab. (INL), Idaho Falls, ID (United States)
- Sponsoring Organization:
- USDOE Office of Nuclear Energy (NE)
- Grant/Contract Number:
- AC07-05ID14517
- OSTI ID:
- 1244688
- Alternate ID(s):
- OSTI ID: 1244689
- Report Number(s):
- INL/JOU-14-33448
- Journal Information:
- Nuclear Technology, Vol. 193, Issue 1; ISSN 0029-5450
- Publisher:
- American Nuclear Society (ANS)Copyright Statement
- Country of Publication:
- United States
- Language:
- English
Web of Science
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