Numerical assessment for entry condition of severe accident management guidelines in a Swedish nuclear power plant

Paks Nuclear Power Plant identified the post-Fukushima actions for mitigation and management of severe accidents caused by external events that include updating of some hazard assessments, evaluation of capacity / margins of existing severe accident management facilities, and construction of some mew systems and facilities. In all cases, the basic question was, what level of margin has to be ensured above design basis external hazard effects, and what level of or hazard has to be taken for the design. Paks Nuclear Power Plant developed certain an applicable in the practice concept for the qualification of already implemented and design the new post-Fukushima measures that is outlined in the paper. The concept and practice is presented on several examples.

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Analysis of Severe Accident Management Strategy for a BWR-4 Nuclear Power Plant

Nuclear Technology ◽

10.13182/nt05-a3674 ◽

2005 ◽

Vol 152 (3) ◽

pp. 253-265 ◽

Cited By ~ 9

Author(s):

Te-Chuan Wang ◽

Shih-Jen Wang ◽

Jyh-Tong Teng

Keyword(s):

Power Plant ◽

Nuclear Power Plant ◽

Management Strategy ◽

Nuclear Power ◽

Severe Accident ◽

Accident Management

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Design of Severe Accident Management Systems for Beyond Design Basis External Hazards at Paks Nuclear Power Plant

Journal of Nuclear Engineering and Radiation Science ◽

10.1115/1.4037715 ◽

2018 ◽

Vol 4 (2) ◽

Author(s):

Tamás János Katona ◽

András Vilimi

Keyword(s):

Power Plant ◽

Nuclear Power Plant ◽

Nuclear Power ◽

Severe Accident ◽

Exceedance Probability ◽

Basic Question ◽

Existing Structures ◽

Design Basis ◽

Accident Management ◽

Definition Of

Paks Nuclear Power Plant (NPP) identified the post-Fukushima actions for mitigation and management of severe accidents caused by external events that include updating of some hazard assessments, evaluation of margins of existing severe accident management (SAM) facilities, and construction of some new systems and facilities. While developing the SAM strategy, the basic question was what is the sufficient margin above the design basis level of existing structures, systems, and components for avoiding the cliff-edge effects, and what level of or hazard should be taken for the design of new structures and systems dedicated for SAM. Paks NPP developed an applicable in the practice concept for the qualification of already implemented SAM measures and design the new post-Fukushima measures that are outlined in the paper. The concept is based on the generalization of the procedure and assumptions used in the definition of acceptable margins for seismic loads, analysis of the steepness of the hazard curves and features of the hazards. Justification of the definition of exceedance probability of the design basis effects for the design of SAM systems is given based on the first order reliability theory. The application of the concept is presented on several practical examples.

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Severe Accident Steady-State Modeling of Advanced Nuclear Power Plant Based on ASTEC Code

Volume 6: Thermal-Hydraulics ◽

10.1115/icone25-67842 ◽

2017 ◽

Author(s):

Wei Song ◽

Jiaxu Zuo ◽

Yan Chen ◽

Chaojun Li ◽

Peng Zheng

Keyword(s):

Steady State ◽

Power Plant ◽

Nuclear Power Plant ◽

Nuclear Power ◽

Severe Accident ◽

Cooling Systems ◽

Accident Management ◽

Management Guidance ◽

Level 2 ◽

Reactor Block

Severe accident is an attractive topic today for the nuclear power plant (NPP) safety. In the nuclear safety regulatory work, it is planned to build a full scale severe accident model for the advanced nuclear power plant of China to study the new designs of severe accident prevention and mitigation systems and strategies, and to further deploy the application on the level 2 PSA and severe accident management guidance. This paper firstly introduces the modeling tool, ASTEC, and then presents the progress of modeling work, which is mainly on the steady state modeling and regulation including reactor block, primary and secondary cooling systems, regulation systems etc. Last but not least, the work plan for the future is given.

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