scholarly journals Severe Accident Management Systems and Procedures

Hadmérnök ◽  
2021 ◽  
Vol 16 (3) ◽  
pp. 41-54
Author(s):  
Zoltán Antal
Keyword(s):  
Nuclear Power ◽  
New Technologies ◽  
Damage Control ◽  
Severe Accident ◽  
Safe Operation ◽  
Safety Measures ◽  
Procedure Guidelines ◽  
Accident Management ◽  
Optimal Efficiency ◽  
Definition Of

A nuclear power plant’s safe operation involves the planning for non-standard operational emergencies, where  pre-determined safety measures and damage control interventions must be taken into consideration depending  on the developed event. A nuclear power plant’s safe  operation involves the planning for non-standard  operational emergencies, where pre-determined safety  measures and damage control interventions must be taken  into consideration depending on the developed event. The  definition of the severe accident management cannot be  explained in a single concept, it needs to be examined in  detail. As a result of this it becomes necessary to specify the procedure guidelines appropriate to the nature of the event, which can be used with optimal efficiency under  hierarchical organisational control. The experience of  nuclear accidents in the world and the precognition of  future events, the knowledge of existing guidelines for  severe accident management needs to be deepened  continuously, but at the same time it can be parallelly  upgraded with the application of new technologies. 

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

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.

scholarly journals A decision-support approach to severe accident management in nuclear power plants

2020 ◽  
pp. 1-12
Author(s):  
Marko Bohanec ◽  
Ivan Vrbanić ◽  
Ivica Bašić ◽  
Klemen Debelak ◽  
Luka Štrubelj
Keyword(s):  
Decision Support ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Severe Accident ◽  
Accident Management

Chinese Public and Nuclear Experts May Have Different Perceptions Of Severe Nuclear Accidents

2021 ◽  
Author(s):  
Hsingtzu Wu ◽  
Leyao Huang
Keyword(s):  
Nuclear Power ◽  
Nuclear Accident ◽  
Severe Accident ◽  
The Public ◽  
Severe Accidents ◽  
White Collar Workers ◽  
Questionnaire Surveys ◽  
Definition Of ◽  
Chinese Public ◽  
Severe Nuclear Accident

Abstract Nuclear power has been a controversial social issue, and societal acceptance is critical to its development and future. In addition, risk informed rules and regulations rely on the public’s understanding. However, there seems a communication gap about nuclear safety between nuclear experts and the public in China, and three questionnaire surveys were conducted to better understand Chinese public’s perceptions of a severe nuclear accident. The sample sizes were 117, 280 and 1071. Most of the respondents were students or white-collar workers born after 1990. In these three surveys, we found that more than 85% of respondents consider a less severe accident as a severe nuclear accident, and most respondents considered an incident to constitute a severe nuclear accident. The results demonstrate that nuclear experts and Chinese public may have different definitions of a severe nuclear accident. Therefore, we suggest that the definition of severe accidents should be better explained to the public to benefit the communication about risk informed rules and regulations. In addition, our three different surveys yielded a similar result, and we anticipate that a questionnaire survey with a larger sample size would do the same.

Analysis of Complexity in Nuclear Power Severe Accident Management

1993 ◽  
Vol 37 (4) ◽  
pp. 377-381 ◽  
Author(s):  
Randall J. Mumaw ◽  
Emilie M. Roth ◽  
Isabelle Schoenfeld
Keyword(s):  
Decision Making ◽  
Cognitive Skills ◽  
Nuclear Power ◽  
Human Error ◽  
Severe Accident ◽  
Emergency Operations ◽  
Accident Management ◽  
Potential Sources ◽  
Plant Operations ◽  
Analysis Of Performance

A model of decision making has been developed for nuclear power plant operations and has been previously applied to the analysis of performance during emergency operations. The model was extended to identify the cognitive skills required, the types of complexity that can arise, and the potential for human error in severe accident management (SAM). Twelve SAM scenarios were developed to aid in this analysis. Potential sources of complexity and error are described and illustrated, and implications for training cognitive skills are discussed.

Design of Severe Accident Management Systems for Beyond Design Basis External Hazards at Paks NPP

2016 ◽  
Author(s):  
Tamás János Katona ◽  
András Vilimi
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Severe Accident ◽  
Management Systems ◽  
Basic Question ◽  
Severe Accidents ◽  
Design Basis ◽  
Accident Management ◽  
External Events

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.

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

2005 ◽  
Vol 152 (3) ◽  
pp. 253-265 ◽  
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

Issues Associated With the Development of Severe Accident Management Guidelines for NPPs in China

2013 ◽  
Author(s):  
Zhiyi Yang ◽  
Yimin Chong ◽  
Chun Li ◽  
Jian Deng ◽  
Xianhong Xu ◽  
...  
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Severe Accident ◽  
Regulatory Body ◽  
Control Room ◽  
Technical Approach ◽  
Management Guidelines ◽  
Accident Management ◽  
Term Monitoring

After Fukushima nuclear accident, the Severe Accident Management Guidelines (SAMGs) are required according to the policy of the regulatory body in China. Most nuclear power plants (NPPs) in China adopt the technical approach of generic-SAMG of the Westinghouse Owner Group, consisting of severe accident control room guideline (SACRG), diagnostic flow chart (DFC), severe accident guideline (SAG), severe challenge status tree (SCST), severe challenge guideline (SCG), technical support center (TSC) long term monitoring guideline, and SAMG termination guideline (SAEG). A number of issues have been identified during the development of the SAMGs for M310+ NPPs, which is a dominant reactor type in China. The paper discussed these issues and identified some considerations for their resolution.

Causes and Radiological Consequences of the Chernobyl and Fukushima Nuclear Accidents

2018 ◽  
Vol 4 (2) ◽  
Author(s):  
L. Sihver ◽  
N. Yasuda
Keyword(s):  
Local Time ◽  
Emergency Response ◽  
Nuclear Power ◽  
Power Plants ◽  
Severe Accident ◽  
Nuclear Accidents ◽  
Emergency Response System ◽  
Response System ◽  
Accident Management ◽  
Fukushima Daiichi

In this paper, the causes and the radiological consequences of the explosion of the Chernobyl reactor occurred at 1:23 a.m. (local time) on Apr. 26, 1986, and of the Fukushima Daiichi nuclear disaster following the huge Tsunami caused by the Great East Japan earthquake at 2.46 p.m. (local time) on Mar. 11, 2011 are discussed. The need for better severe accident management (SAM), and severe accident management guidelines (SAMGs), are essential in order to increase the safety of the existing and future operating nuclear power plants (NPPs). In addition to that, stress tests should, on a regular basis, be performed to assess whether the NPPs can withstand the effects of natural disasters and man-made failures and actions. The differences in safety preparations at the Chernobyl and Fukushima Daiichi will therefore be presented, as well as recommendations concerning improvements of safety culture, decontamination, and disaster planning. The need for a high-level national emergency response system in case of nuclear accidents will be discussed. The emergency response system should include fast alarms, communication between nuclear power plants, nuclear power authorities and the public people, as well as well-prepared and well-established evacuation plans and evacuation zones. The experiences of disaster planning and the development of a new improved emergency response system in Japan will also be presented together with the training and education program, which have been established to ensure that professional rescue workers, including medical staff, fire fighters, and police, as well as the normal populations including patients, have sufficient knowledge about ionizing radiation and are informed about the meaning of radiation risks and safety.

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