An overview of protective action decision-making for a nuclear power plant emergency

After Fukushima nuclear power plant accident, severe accident is getting more and more concerns all over the world. In order to mitigate severe accident and improve the safety of nuclear power plant, two different strategies are applied in different plants. One is in-vessel melt retention strategy, and the other is ex-vessel melt retention strategy. Tianwan nuclear power plant is an improved Gen II nuclear power plant and in-vessel melt retention strategy is adopted in the plant. In order to achieve this strategy, cavity injection system is designed for the plant. Probabilistic Safety Analysis is the most commonly used quantitative risk assessment tool for decision-making in selecting the optimal design among alternative options. For this plant, in order to optimize the design of cavity injection system, improve the safety level of nuclear power plant, and meanwhile, improve the engineering implementation and economization, Level 2 PSA was used for this decision-making process. In this paper, the Level 2 PSA for this plant and the application for the design of cavity injection system are introduced.

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Evaluating Nuclear Control Room Improvements Through Analysis of Critical Operator Decisions

Proceedings of the Human Factors Society Annual Meeting ◽

10.1177/107118138102500125 ◽

1981 ◽

Vol 25 (1) ◽

pp. 100-104 ◽

Cited By ~ 1

Author(s):

Richard W. Pew ◽

Duncan C. Miller ◽

Carl E. Feehrer

Keyword(s):

Decision Making ◽

Power Plant ◽

Nuclear Power Plant ◽

Nuclear Power ◽

Control Room ◽

Time Stress ◽

Nuclear Control ◽

Potential Impact

Decision making by nuclear power plant operators was studied in the context of four recent “off-normal” incidents, in order to assess the potential impact of various proposed control room improvements. A model of operator decision making was applied to critical operator decisions during each event in order to determine how each proposed improvement could help prevent or resolve decision-making errors. The results indicated that time stress on the crew played an appreciable role in the performance failures identified, and that a combination of improvements will be necessary to address this problem.

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Operational personnel decision-making supportautomatic system at nuclear power plant generating unitsby criterion of technical economic efficiency with dueconsideration of reliability factors

Nuclear and Radiation Safety ◽

10.32918/nrs.2018.2(78).02 ◽

2018 ◽

pp. 11-19

Author(s):

A. Yefimov ◽

D. Kukhtin ◽

T. Potanina ◽

T. Harkusha ◽

V. Kavertsev

Keyword(s):

Decision Making ◽

Power Plant ◽

Nuclear Power Plant ◽

Nuclear Power ◽

Description Logic ◽

Oriented Graph ◽

Flow Diagram ◽

Imitation Model ◽

Operation Efficiency ◽

Nuclear Power Plant Unit

New methods and approaches to development of nuclear power plant unit imitation models development. An imitation model is proposed for nuclear power plant unit developed on the basis of oriented graph applied to unit flow diagram description logic-numerical operators for calculation of parameters and characteristics determining its operation efficiency, reliability and safety. Automatic system is described developed on the basis of imitation model for decision-making support, applied to analysis of VVER nuclear power plant unit operation efficiency with due consideration of equipment operation reliability and safety indices.

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