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Published May 2021 | Version v1
Journal article

Multicriterion benefit evaluation methodology for safety enhancements in nuclear power plants and application for FLEX strategies

  • 1. Idaho National Laboratory, 2525 Fremont Avenue, Idaho Falls, ID, 83415 (United States)

Description

Highlights: • A multicriterion benefit evaluation method is proposed for nuclear power plant safety enhancements. • Evaluation criteria include public risk, occupational risk, plant cost and revenue. • Correlations and causations among evaluation criteria are modeled. • Decision maker's preferences of plant safety and economics are reflected. • A nuclear power plant safety enhancement, FLEX strategy, is evaluated as a case study. This paper proposes a multicriterion benefit evaluation (MCBE) methodology for evaluating costs and benefits of implementing safety enhancements in nuclear power plants. The MCBE methodology establishes a comprehensive evaluation scope using multiple evaluation criteria (including public risk, occupational risk, plant revenue, and plant cost) and multiple contexts (including plant normal operations, incidents, and accidents). The MCBE methodology formulates a benefit or cost element as the product of a monetary consequence and its occurrence-likelihood change. The MCBE methodology also incorporates a decision maker' preferences toward occurrence likelihood and monetary consequence into cost and benefit estimations through a modified usage of cumulative prospect theory. This paper applies the MCBE methodology to the implementation of diverse and flexible coping strategy (FLEX) in a generic nuclear power plant as an illustrative example. The FLEX benefits are evaluated through three types of influence paths: plant safety enhancement, risk-informed activities, and potential additional credit of FLEX in supporting plant operation and maintenance-efficiency improvement. The benefit-to-cost ratio (BCR) of FLEX implementation is calculated. Sensitivity analyses are conducted to examine the impacts of modeling assumptions and input parameter values on the BCR.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.nucengdes.2021.111135

Additional details

Identifiers

DOI
10.1016/j.nucengdes.2021.111135;
PII
S002954932100087X;

Publishing Information

Journal Title
Nuclear Engineering and Design
Journal Volume
376
Journal Page Range
vp.
ISSN
0029-5493
CODEN
NEDEAU

INIS

Country of Publication
Netherlands
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
54014763
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Descriptors DEI
COMPUTERIZED SIMULATION; CORRELATIONS; EFFICIENCY; NUCLEAR POWER PLANTS; REACTOR OPERATION; SENSITIVITY ANALYSIS
Descriptors DEC
NUCLEAR FACILITIES; OPERATION; POWER PLANTS; REACTOR LIFE CYCLE; SIMULATION; THERMAL POWER PLANTS

Optional Information

Copyright
Copyright (c) 2021 Elsevier B.V. All rights reserved.