Probabilistic Analysis of Creep-Induced SGTR for NPP

2018 ◽  
Author(s):  
Wenjing Li ◽  
Wentao Zhu ◽  
Xinli Yu ◽  
Wei Wei
Keyword(s):  
Radioactive Material ◽  
Severe Accident ◽  
Accident Analysis ◽  
Creep Failure ◽  
Analysis Methodology ◽  
Accident Management ◽  
Temperature And Pressure ◽  
Technical Basis ◽  
Steam Generator Tubes ◽  
Level 2

Severe accident analysis is the technical basis of severe accident prevention and mitigation, and severe accident phenomenon analysis can provide important technical support for Level-2 Probabilistic Safety Analysis (L2 PSA) and severe accident management of NPP. This paper evaluates the probability of creep-induced steam generator tubes rupture (SGTR) which might lead to direct release of radioactive material to environment based on Risk-Oriented Accident Analysis Methodology (ROAAM). According to Larson-Miller creep failure model, the material parameters are provided first, then a two-loop NPP model is established with MAAP4 code to assess the temperature and pressure of the pipes for typical sequences, and eventually the probability of creep-induced SGTR phenomenon for typical sequences is calculated.

scholarly journals Perspectives on a Severe Accident Consequences—10 Years after the Fukushima Accident

2021 ◽  
Vol 2 (4) ◽  
pp. 398-411
Author(s):  
Jinho Song
Keyword(s):  
Nuclear Reactor ◽  
Severe Accident ◽  
Accident Analysis ◽  
Fukushima Accident ◽  
The Public ◽  
Analysis Methodology ◽  
International Attention ◽  
Nuclear Reactor Safety ◽  
Term Monitoring

Scientific issues that draw international attention from the public and experts during the last 10 years after the Fukushima accident are discussed. An assessment of current severe accident analysis methodology, impact on the views of nuclear reactor safety, dispute on the safety of fishery products, discharge of radioactive water to the ocean, status of decommissioning, and needs for long-term monitoring of the environment are discussed.

A Modeling Method of the Branch Probability of the Temperature-Induced SGTR Phenomenon

2017 ◽  
Author(s):  
Zibin Liu ◽  
Dingqing Guo ◽  
Bing Zhang ◽  
Jinkai Wang
Keyword(s):  
Steam Generator ◽  
Nuclear Power ◽  
Power Plants ◽  
Modeling Method ◽  
Radioactive Material ◽  
Severe Accident ◽  
Steam Generator Tube ◽  
Modeling Methods ◽  
Radioactive Release ◽  
Level 2

The phenomenon of temperature-induced steam generator tube rupture (TI-SGTR) is a typical phenomenon in the severe accident process of nuclear power plants. The occurrence of the phenomenon may result in the radioactive material bypass the containment, causing a large radioactive release. This paper investigates modeling methods of the phenomenon of temperature-induced SGTR in level 2 PSA and presents an optimizing modeling method to calculate the probability of branching probability of TI-SGTR, aiming at improving the rationality and veracity of level 2 PSA.

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

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.

Research and Development of Validation and Drill System for Full Scope of Severe Accident Management Guideline

2017 ◽  
Vol 3 (4) ◽  
Author(s):  
Zhifei Yang ◽  
Yali Chen ◽  
Hu Luo
Keyword(s):  
Research And Development ◽  
Computer Code ◽  
Severe Accident ◽  
Accident Analysis ◽  
Spent Fuel ◽  
Accident Management ◽  
Analysis Computer ◽  
Spent Fuel Pool ◽  
Accident Scenarios ◽  
Drill System

To respond to the urgent needs of verification, training, and drill for full scope severe accident management guidelines (FSSAMG) among nuclear regulators, utilities, and research institutes, the FSSAMG verification and drill system is developed. The FSSAMG includes comprehensive scenarios under power condition, shutdown condition, spent fuel pool (SFP) condition, and refueling conditions. This article summarized the research and development of validation and drill system for FSSAMG by using the severe accident analysis computer code modular accident analysis program 5 (MAAP5). Realistic accident scenarios can be verified and exercised in the developed system to support FSSAMG training, drill, examination, and verification.

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