A forward-backward coupled source term estimation for nuclear power plant accident: A case study of loss of coolant accident scenario

2017 ◽  
Vol 104 ◽  
pp. 64-74 ◽  
Author(s):  
Sida Sun ◽  
Hong Li ◽  
Sheng Fang
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Source Term ◽  
Nuclear Power Plant Accident ◽  
Accident Scenario ◽  
Loss Of Coolant Accident ◽  
Loss Of Coolant ◽  
Source Term Estimation

A Simulation of Small Break Loss of Coolant Accident (SB-LOCA) in AP1000 Nuclear Power Plant Using RELAP5-MV

2017 ◽  
Author(s):  
Eltayeb Yousif ◽  
Zhang Zhijian ◽  
Tian Zhao-fei ◽  
A. M. Mustafa
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Power Systems ◽  
Nuclear Power ◽  
Power Plants ◽  
Computational Simulation ◽  
Primary System ◽  
Transient Time ◽  
Loss Of Coolant Accident ◽  
Loss Of Coolant

To ensure effective operation of nuclear power plants, it is very important to evaluate different accident scenarios in actual plant conditions with different codes. In the field of nuclear safety, Loss of Coolant Accident (LOCA) is one of the main accidents. RELAP-MV Visualized Modularization software technology is recognized as one of the best estimated transient simulation programs of light water reactors, and also has the options for improved modeling methods, advanced programming, computational simulation techniques and integrated graphics displays. In this study, transient analysis of the primary system variation of thermo-hydraulics parameters in primary loop under SB-LOCA accident in AP1000 nuclear power plant (NPP) is carried out by Relap5-MV thermo-hydraulics code. While focusing on LOCA analysis in this study, effort was also made to test the effectiveness of the RELAP5-MV software already developed. The accuracy and reliability of RELAP5-MV have been successfully confirmed by simulating LOCA. The calculation was performed up to a transient time of 4,500.0s. RELAP5-MV is able to simulate a nuclear power system accurately and reliably using this modular modeling method. The results obtained from RELAP5 and RELAP5-MV are in agreement as they are based on the same models though in comparison with RELAP5, RELAP5-MV makes simulation of nuclear power systems easier and convenient for users most especially for the beginners.

scholarly journals Differentiation and Integration of Evacuees with Regard to Lifting the Evacuation Order Following the Nuclear Power Plant Accident: A Case Study of Naraha and Tomioka Towns, Futaba District, Fukushima Prefecture

2018 ◽  
Vol 13 (6) ◽  
pp. 1125-1141
Author(s):  
Michimasa Matsumoto ◽  
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Entire Area ◽  
Nuclear Power Plant Accident ◽  
Fukushima Prefecture ◽  
Before And After ◽  
Questionnaire Surveys

As of spring 2018, evacuation orders have been lifted from the entire area of Naraha Town and most of Tomioka, except for certain areas. While many evacuees have chosen their evacuation destinations as their permanent residences, some have returned to their former towns. This paper examines the factors involved in the “differentiation” and “integration” of Naraha and Tomioka residents before and after the disaster and the various forms they assume, based on the results of questionnaire surveys conducted in 2012 and 2015 as well as interviews conducted on a continuing basis since the disaster. In this process, it has become apparent that a split exists between Naraha, whose residents are moving toward “integration” with the lifting of the evacuation order, and Tomioka, whose residents are progressing toward “differentiation.”

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