A review for identification and selection of initiating events important for Level 1 probabilistic safety assessment study for a 10 MW water water research reactor (VVR)

Annals of Nuclear Energy ◽

10.1016/j.anucene.2018.01.039 ◽

2018 ◽

Vol 115 ◽

pp. 303-314

Author(s):

F. Ameyaw ◽

R.G. Abrefah ◽

S. Yamoah ◽

J.J. Fletcher ◽

S.A. Birikorang

Keyword(s):

Safety Assessment ◽

Research Reactor ◽

Water Research ◽

Probabilistic Safety Assessment ◽

Assessment Study ◽

Level 1 ◽

Selection Of ◽

Probabilistic Safety

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Selection of important initiating events for Level 1 probabilistic safety assessment study at Puspati TRIGA Reactor

Annals of Nuclear Energy ◽

10.1016/j.anucene.2016.01.047 ◽

2016 ◽

Vol 92 ◽

pp. 198-210 ◽

Author(s):

M. Maskin ◽

F. Charlie ◽

A. Hassan ◽

P. Prak Tom ◽

Z. Ramli ◽

...

Keyword(s):

Safety Assessment ◽

Triga Reactor ◽

Probabilistic Safety Assessment ◽

Assessment Study ◽

Level 1 ◽

Selection Of ◽

Probabilistic Safety

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Application of Hazard and Operability Technique to Level 1 Probabilistic Safety Assessment of Thai Research Reactor-1/Modification 1: Internal Events and Human Errors

Progress in Nuclear Energy ◽

10.1016/j.pnucene.2021.103838 ◽

2021 ◽

pp. 103838

Author(s):

Wasin Vechgama ◽

Kampanart Silva ◽

Anantachai Pechrak ◽

Saensuk Wetchagarun

Keyword(s):

Safety Assessment ◽

Research Reactor ◽

Human Errors ◽

Probabilistic Safety Assessment ◽

Level 1 ◽

Probabilistic Safety

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Quantification of initiating event frequencies and component reliability data in level 1 probabilistic safety assessment at Puspati TRIGA research reactor

Annals of Nuclear Energy ◽

10.1016/j.anucene.2018.07.013 ◽

2018 ◽

Vol 121 ◽

pp. 22-28 ◽

Author(s):

M. Maskin ◽

A. Hassan ◽

F.C. Brayon ◽

P.T. Phongsakorn ◽

M.F. Zakaria ◽

...

Keyword(s):

Safety Assessment ◽

Research Reactor ◽

Reliability Data ◽

Component Reliability ◽

Probabilistic Safety Assessment ◽

Level 1 ◽

Probabilistic Safety

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Level 1 probabilistic safety assessment to support the design of the CEA 2400 MWth gas-cooled fast reactor

Nuclear Engineering and Design ◽

10.1016/j.nucengdes.2010.09.003 ◽

2010 ◽

Vol 240 (11) ◽

pp. 3758-3780 ◽

Author(s):

C. Bassi ◽

Ph. Azria ◽

M. Balmain

Keyword(s):

Fast Reactor ◽

Safety Assessment ◽

Probabilistic Safety Assessment ◽

Level 1 ◽

Probabilistic Safety

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Application of probabilistic safety assessment to parameters of operational limits and conditions of the opal research reactor

Australian Journal of Mechanical Engineering ◽

10.1080/14484846.2008.11464541 ◽

2008 ◽

Vol 5 (2) ◽

pp. 127-137

Author(s):

S J Bastin ◽

J Perera

Keyword(s):

Safety Assessment ◽

Research Reactor ◽

Probabilistic Safety Assessment ◽

Probabilistic Safety

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Probabilistic Safety Assessment of Tehran research reactor based on a synergy between plant topology and hierarchical evolutions

Progress in Nuclear Energy ◽

10.1016/j.pnucene.2013.10.003 ◽

2014 ◽

Vol 70 ◽

pp. 199-208 ◽

Author(s):

Ramin Barati ◽

Saeed Setayeshi

Keyword(s):

Safety Assessment ◽

Research Reactor ◽

Probabilistic Safety Assessment ◽

Tehran Research Reactor ◽

Probabilistic Safety

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A design-phase probabilistic safety assessment of a research reactor to enhance its safety

Annals of Nuclear Energy ◽

10.1016/j.anucene.2019.04.007 ◽

2019 ◽

Vol 131 ◽

pp. 367-377

Author(s):

Yoon-Hwan Lee

Keyword(s):

Safety Assessment ◽

Research Reactor ◽

Design Phase ◽

Probabilistic Safety Assessment ◽

Probabilistic Safety

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An Introductory Course of the Probabilistic Safety Assessment (PSA) for LWR―(3) Level 1 PSA for Internal Events

Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan ◽

10.3327/jaesj.48.409 ◽

2006 ◽

Vol 48 (6) ◽

pp. 409-417 ◽

Author(s):

Ken MURAMATSU

Keyword(s):

Safety Assessment ◽

Probabilistic Safety Assessment ◽

Introductory Course ◽

Level 1 ◽

Probabilistic Safety

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Improved research reactor probabilistic safety assessment with an increased amount of plant-specific data / Verbesserte probabilistische Sicherheitsanalyse für einen Forschungsreaktor bei verstärkter Verwendung anlagenspezifischer Daten.

Kerntechnik ◽

10.1515/kern-1993-580617 ◽

1993 ◽

Vol 58 (6) ◽

pp. 358-362

Author(s):

C. Kirchsteiger ◽

H. Böck

Keyword(s):

Safety Assessment ◽

Research Reactor ◽

Specific Data ◽

Probabilistic Safety Assessment ◽

Probabilistic Safety

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Application of Bayesian Statistics to Probabilistic Safety Assessment of Thai Research Reactor-1/ Modification 1

Proceedings of the 30th European Safety and Reliability Conference and 15th Probabilistic Safety Assessment and Management Conference ◽

10.3850/978-981-14-8593-0_3651-cd ◽

2020 ◽

Author(s):

Wasin Vechgama ◽

Kampanart Silva ◽

Anantachai Pechrak ◽

Saensuk Wetchagarun

Keyword(s):

Bayesian Statistics ◽

Safety Assessment ◽

Research Reactor ◽

Probabilistic Safety Assessment ◽

Probabilistic Safety

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