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Title: Risk-Informed Safety Analysis for Accident Tolerant Fuels

Abstract

Accident Tolerant Fuels (ATF) are being tested by different nuclear vendors and research organizations and their introduction in the US light water reactors fleet is planned for the second half of the 2020`s. In the framework of the US-DOE Light-Water Reactor Sustainability program, Risk-Informed Systems Analysis pathway, researches are being conducted at the Idaho National Laboratory for developing tools and methods that can help the industry quantifying the benefits from the adoption of ATF technology. In this paper we describe the developed risk-informed methodology including the safety analysis codes improvements, and we present some results for selected accident scenarios. The developed methodology combines INL state-of-the-art deterministic Best Estimate code RELAP5-3D, and Probabilistic Risk Analysis tools RAVEN and SAPHIRE. The analyses are performed on a three-loops pressurized water reactor, simulating Station Blackout and LB-LOCA accidents and considering near-term ATFs, or FeCrAl and Chromium-coated clads. Finally, we show how, applying our methodology, the new Core Damage Frequency can be assessed. The results indicated that the main benefits in introducing near-term ATFs concern a significant reduction in the hydrogen production during accident conditions. No significant Core Damage Frequency reduction was found.

Authors:
ORCiD logo [1]; ORCiD logo [1]; ORCiD logo [1]; ORCiD logo [1]; ORCiD logo [1]
  1. Idaho National Lab. (INL), Idaho Falls, ID (United States)
Publication Date:
Research Org.:
Idaho National Lab. (INL), Idaho Falls, ID (United States)
Sponsoring Org.:
USDOE Office of Energy Efficiency and Renewable Energy (EERE)
OSTI Identifier:
1634778
Report Number(s):
INL/JOU-19-56840-Rev000
Journal ID: ISSN 0029-5639
Grant/Contract Number:  
AC07-05ID14517
Resource Type:
Accepted Manuscript
Journal Name:
Nuclear Science and Engineering
Additional Journal Information:
Journal Volume: 194; Journal Issue: 8-9; Journal ID: ISSN 0029-5639
Publisher:
American Nuclear Society - Taylor & Francis
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; 22 GENERAL STUDIES OF NUCLEAR REACTORS; Risk-Informed Analysis; Accident Tolerant Fuels; RELAP5-3D; Station Blackout; LB-LOCA

Citation Formats

Parisi, Carlo, Ma, Zhegang, Mandelli, Diego, Anderson, Nolan A, and Zhang, Hongbin. Risk-Informed Safety Analysis for Accident Tolerant Fuels. United States: N. p., 2020. Web. doi:10.1080/00295639.2020.1732699.
Parisi, Carlo, Ma, Zhegang, Mandelli, Diego, Anderson, Nolan A, & Zhang, Hongbin. Risk-Informed Safety Analysis for Accident Tolerant Fuels. United States. doi:https://doi.org/10.1080/00295639.2020.1732699
Parisi, Carlo, Ma, Zhegang, Mandelli, Diego, Anderson, Nolan A, and Zhang, Hongbin. Wed . "Risk-Informed Safety Analysis for Accident Tolerant Fuels". United States. doi:https://doi.org/10.1080/00295639.2020.1732699. https://www.osti.gov/servlets/purl/1634778.
@article{osti_1634778,
title = {Risk-Informed Safety Analysis for Accident Tolerant Fuels},
author = {Parisi, Carlo and Ma, Zhegang and Mandelli, Diego and Anderson, Nolan A and Zhang, Hongbin},
abstractNote = {Accident Tolerant Fuels (ATF) are being tested by different nuclear vendors and research organizations and their introduction in the US light water reactors fleet is planned for the second half of the 2020`s. In the framework of the US-DOE Light-Water Reactor Sustainability program, Risk-Informed Systems Analysis pathway, researches are being conducted at the Idaho National Laboratory for developing tools and methods that can help the industry quantifying the benefits from the adoption of ATF technology. In this paper we describe the developed risk-informed methodology including the safety analysis codes improvements, and we present some results for selected accident scenarios. The developed methodology combines INL state-of-the-art deterministic Best Estimate code RELAP5-3D, and Probabilistic Risk Analysis tools RAVEN and SAPHIRE. The analyses are performed on a three-loops pressurized water reactor, simulating Station Blackout and LB-LOCA accidents and considering near-term ATFs, or FeCrAl and Chromium-coated clads. Finally, we show how, applying our methodology, the new Core Damage Frequency can be assessed. The results indicated that the main benefits in introducing near-term ATFs concern a significant reduction in the hydrogen production during accident conditions. No significant Core Damage Frequency reduction was found.},
doi = {10.1080/00295639.2020.1732699},
journal = {Nuclear Science and Engineering},
number = 8-9,
volume = 194,
place = {United States},
year = {2020},
month = {3}
}

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