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Title: Light Water Reactor Sustainability Program: Analysis of Pressurized Water Reactor Station Blackout Caused by External Flooding Using the RISMC Toolkit

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. 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 insight to decision makers through a series of simulations of the plant dynamics for different initial conditions (e.g., probabilistic analysis and uncertainty quantification). This report focuses, in particular, on the application of a RISMC detailed demonstration case study for an emergent issue using the RAVEN and RELAP-7 tools. This case study looks at the impact of a couple of challenges to a hypothetical pressurized water reactor, including: (1) a power uprate, (2) a potential loss of off-site power followed by the possible loss of all diesel generators (i.e., a station black-out event), (3) and earthquake induces station-blackout, and (4) a potential earthquake induced tsunami flood. The analysis is performed by using a set of codes: a thermal-hydraulic code (RELAP-7), a flooding simulation tool (NEUTRINO) and a stochastic analysis tool (RAVEN) – these are currently under development at the Idaho National Laboratory.
Authors:
 [1] ;  [1] ;  [1] ;  [1] ;  [1] ;  [1] ;  [1]
  1. Idaho National Lab. (INL), Idaho Falls, ID (United States)
Publication Date:
OSTI Identifier:
1168617
Report Number(s):
INL/EXT--14-32906
TRN: US1500007
DOE Contract Number:
AC07-05ID14517
Resource Type:
Technical Report
Research Org:
Idaho National Lab. (INL), Idaho Falls, ID (United States)
Sponsoring Org:
USDOE Office of Nuclear Energy (NE)
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; PWR TYPE REACTORS; REACTOR SAFETY; RISK ASSESSMENT; SAFETY MARGINS; NUCLEAR POWER PLANTS; IDAHO NATIONAL LABORATORY; THERMAL HYDRAULICS; MONTE CARLO METHOD; PROBABILISTIC ESTIMATION; N CODES; R CODES; OUTAGES; EARTHQUAKES; TSUNAMIS; FLOODS; SUSTAINABILITY; STOCHASTIC PROCESSES; REACTOR ACCIDENTS; AUGMENTATION; LIFETIME EXTENSION; MANAGEMENT; PERFORMANCE; PROFITS; COMPUTERIZED SIMULATION BWR; SBO; flooding; limit surface; PRA; dynamic PRA