Seismic probabilistic safety analysis of unit 1 of the Loviisa nuclear power plant

1996 ◽  
Vol 160 (3) ◽  
pp. 411-426
Author(s):  
P. Varpasuo ◽  
J. Puttonen ◽  
M.K. Ravindra
Author(s):  
Wei Gao ◽  
Guofeng Tang ◽  
Jingyu Zhang ◽  
Qinfang Zhang

Seismic risk of nuclear power plant has drawn increasing attention after Fukushima accident. An intensive study has been carried out in this paper, including sampling of component and structure fragility based on Monte Carlo method, fragility analysis on system or plant level, convolution of seismic hazard curves and fragility curves. To derive more accurate quantification results, the binary decision diagram (BDD) algorithm was introduced into the quantification process, which effectively reduces the deficiency of the conventional method on coping with large probability events and negated logic. Seismic Probabilistic Safety Analysis (PSA/PRA) quantification software was developed based on algorithms discussed in this paper. Tests and application has been made for this software with a specific nuclear power plant seismic PSA model. The results show that this software is effective on seismic PSA quantification.


Author(s):  
Cristian Tudoran

Abstract In the last four decades, as the nuclear industry grew and got mature, the importance of adequate risk evaluating tools became decisive. Therefore, the Probabilistic Risk Assessment (also known as Probabilistic Safety Analysis) became a cornerstone of the decisions in such high energy and high-risk industry. PSA has an internationally recognised standard, and it is supported by a group of highly trained experts, (no more than a few hundred worldwide).This work can be used as a guide for the improving the required individual and teamwork skills needed in a Probabilistic Safety Analysis - PSA Team. The necessity of such a moment in a PSA Training was imagined by Dan Serbanescu, doctor in science, nuclear energy expert, risk and safety analyst, in May 2017. After few discussions and according to recognised international standards (Probabilistic Risk Assessment procedures guide, 1983), a first time delivery was possible in the PSA Training delivered in Centrala Nuclearoelectrica Cernavoda / Nuclear Power Plant Cernavoda (2017).This article presents a systematic approach for team improvement skills, consisting of the observation, presentation of the skills required, the skills practised in the proposed exercises, the techniques used during this module (coaching included), and results. The Purpose of the newly proposed combination of training and coaching methods with the specific traditional one oriented mainly to the technical and procedural skills is to raise participants’ awareness about how soft-skills can be used in the PSA Teamwork. As Nuclear Power Plant can be easily compared with a complex organisation, soft skills are vital to be developed within the teams. PSA is becoming more required not only in nuclear but also in the aerospace industry (it was adopted by NASA - National Aeronautics and Space Administration for all future space program and by some hazardous chemical industries, as also stated in international documents (of the European Commission for instance).


2019 ◽  
Vol 34 (3) ◽  
pp. 238-242
Author(s):  
Rex Abrefah ◽  
Prince Atsu ◽  
Robert Sogbadji

In pursuance of sufficient, stable and clean energy to solve the ever-looming power crisis in Ghana, the Nuclear Power Institute of the Ghana Atomic Energy Commission has on the agenda to advise the government on the nuclear power to include in the country's energy mix. After consideration of several proposed nuclear reactor technologies, the Nuclear Power Institute considered a high pressure reactor or vodo-vodyanoi energetichesky reactor as the nuclear power technologies for Ghana's first nuclear power plant. As part of technology assessments, neutronic safety parameters of both reactors are investigated. The MCNP neutronic code was employed as a computational tool to analyze the reactivity temperature coefficients, moderator void coefficient, criticality and neutron behavior at various operating conditions. The high pressure reactor which is still under construction and theoretical safety analysis, showed good inherent safety features which are comparable to the already existing European pressurized reactor technology.


2013 ◽  
Vol 479-480 ◽  
pp. 543-547
Author(s):  
Jong Rong Wang ◽  
Hao Tzu Lin ◽  
Wan Yun Li ◽  
Shao Wen Chen ◽  
Chun Kuan Shih

In the nuclear power plant (NPP) safety, the safety analysis of the NPP is very important work. In Fukushima NPP event, due to the earthquake and tsunami, the cooling system of the spent fuel pool failed and the safety issue of the spent fuel pool generated. In this study, the safety analysis of the Chinshan NPP spent fuel pool was performed by using TRACE and FRAPTRAN, which also assumed the cooling system of the spent fuel pool failed. There are two cases considered in this study. Case 1 is the no fire water injection in the spent fuel pool. Case 2 is the fire water injection while the water level of the spent fuel pool uncover the length of fuel rods over 1/3 full length. The analysis results of the case 1 show that the failure of cladding occurs in about 3.6 day. However, the results of case 2 indicate that the integrity of cladding is kept after the fire water injection.


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