Development and methodology of level 1 probability safety assessment at PUSPATI TRIGA Reactor

Mazleha Maskin, Phongsakorn Prak Tom, Tonny Anak Lanyau, Fedrick Charlie Matthew Brayon, Faizal K.P. Kunchi Mohamed, Mohamad Fauzi Saad, Ahmad Razali Ismail, Mohamad Puad Haji Abu

Research output: Chapter in Book/Report/Conference proceedingConference contribution

4 Citations (Scopus)

Abstract

As a consequence of the accident at the Fukushima Dai-ichi Nuclear Power Plant in Japan, the safety aspects of the one and only research reactor (31 years old) in Malaysia need be reviewed. Based on this decision, Malaysian Nuclear Agency in collaboration with Atomic Energy Licensing Board and Universiti Kebangsaan Malaysia develop a Level-1 Probability Safety Assessment on this research reactor. This work is aimed to evaluate the potential risks of incidents in RTP and at the same time to identify internal and external hazard that may cause any extreme initiating events. This report documents the methodology in developing a Level 1 PSA performed for the RTP as a complementary approach to deterministic safety analysis both in neutronics and thermal hydraulics. This Level-1 PSA work has been performed according to the procedures suggested in relevant IAEA publications and at the same time numbers of procedures has been developed as part of an Integrated Management System programme implemented in Nuclear Malaysia.

Original languageEnglish
Title of host publicationAIP Conference Proceedings
PublisherAmerican Institute of Physics Inc.
Pages240-244
Number of pages5
Volume1584
ISBN (Print)9780735412163
DOIs
Publication statusPublished - 2014
EventInternational Nuclear Science, Technology and Engineering Conference 2013: Advancing Nuclear Research and Energy Development, iNuSTEC 2013 - Kuala Lumpur
Duration: 30 Sep 20132 Oct 2013

Other

OtherInternational Nuclear Science, Technology and Engineering Conference 2013: Advancing Nuclear Research and Energy Development, iNuSTEC 2013
CityKuala Lumpur
Period30/9/132/10/13

Fingerprint

Malaysia
safety
reactors
methodology
licensing
management systems
nuclear power plants
nuclear energy
accidents
hydraulics
hazards
Japan
causes

Keywords

  • probability safety assessment
  • psa
  • research reactor
  • RTP
  • TRIGA

ASJC Scopus subject areas

  • Physics and Astronomy(all)

Cite this

Maskin, M., Tom, P. P., Lanyau, T. A., Brayon, F. C. M., K.P. Kunchi Mohamed, F., Saad, M. F., ... Abu, M. P. H. (2014). Development and methodology of level 1 probability safety assessment at PUSPATI TRIGA Reactor. In AIP Conference Proceedings (Vol. 1584, pp. 240-244). American Institute of Physics Inc.. https://doi.org/10.1063/1.4866138

Development and methodology of level 1 probability safety assessment at PUSPATI TRIGA Reactor. / Maskin, Mazleha; Tom, Phongsakorn Prak; Lanyau, Tonny Anak; Brayon, Fedrick Charlie Matthew; K.P. Kunchi Mohamed, Faizal; Saad, Mohamad Fauzi; Ismail, Ahmad Razali; Abu, Mohamad Puad Haji.

AIP Conference Proceedings. Vol. 1584 American Institute of Physics Inc., 2014. p. 240-244.

Research output: Chapter in Book/Report/Conference proceedingConference contribution

Maskin, M, Tom, PP, Lanyau, TA, Brayon, FCM, K.P. Kunchi Mohamed, F, Saad, MF, Ismail, AR & Abu, MPH 2014, Development and methodology of level 1 probability safety assessment at PUSPATI TRIGA Reactor. in AIP Conference Proceedings. vol. 1584, American Institute of Physics Inc., pp. 240-244, International Nuclear Science, Technology and Engineering Conference 2013: Advancing Nuclear Research and Energy Development, iNuSTEC 2013, Kuala Lumpur, 30/9/13. https://doi.org/10.1063/1.4866138
Maskin M, Tom PP, Lanyau TA, Brayon FCM, K.P. Kunchi Mohamed F, Saad MF et al. Development and methodology of level 1 probability safety assessment at PUSPATI TRIGA Reactor. In AIP Conference Proceedings. Vol. 1584. American Institute of Physics Inc. 2014. p. 240-244 https://doi.org/10.1063/1.4866138
Maskin, Mazleha ; Tom, Phongsakorn Prak ; Lanyau, Tonny Anak ; Brayon, Fedrick Charlie Matthew ; K.P. Kunchi Mohamed, Faizal ; Saad, Mohamad Fauzi ; Ismail, Ahmad Razali ; Abu, Mohamad Puad Haji. / Development and methodology of level 1 probability safety assessment at PUSPATI TRIGA Reactor. AIP Conference Proceedings. Vol. 1584 American Institute of Physics Inc., 2014. pp. 240-244
@inproceedings{ac83e000cee643eb863ec97f3bb4f9c6,
title = "Development and methodology of level 1 probability safety assessment at PUSPATI TRIGA Reactor",
abstract = "As a consequence of the accident at the Fukushima Dai-ichi Nuclear Power Plant in Japan, the safety aspects of the one and only research reactor (31 years old) in Malaysia need be reviewed. Based on this decision, Malaysian Nuclear Agency in collaboration with Atomic Energy Licensing Board and Universiti Kebangsaan Malaysia develop a Level-1 Probability Safety Assessment on this research reactor. This work is aimed to evaluate the potential risks of incidents in RTP and at the same time to identify internal and external hazard that may cause any extreme initiating events. This report documents the methodology in developing a Level 1 PSA performed for the RTP as a complementary approach to deterministic safety analysis both in neutronics and thermal hydraulics. This Level-1 PSA work has been performed according to the procedures suggested in relevant IAEA publications and at the same time numbers of procedures has been developed as part of an Integrated Management System programme implemented in Nuclear Malaysia.",
keywords = "probability safety assessment, psa, research reactor, RTP, TRIGA",
author = "Mazleha Maskin and Tom, {Phongsakorn Prak} and Lanyau, {Tonny Anak} and Brayon, {Fedrick Charlie Matthew} and {K.P. Kunchi Mohamed}, Faizal and Saad, {Mohamad Fauzi} and Ismail, {Ahmad Razali} and Abu, {Mohamad Puad Haji}",
year = "2014",
doi = "10.1063/1.4866138",
language = "English",
isbn = "9780735412163",
volume = "1584",
pages = "240--244",
booktitle = "AIP Conference Proceedings",
publisher = "American Institute of Physics Inc.",

}

TY - GEN

T1 - Development and methodology of level 1 probability safety assessment at PUSPATI TRIGA Reactor

AU - Maskin, Mazleha

AU - Tom, Phongsakorn Prak

AU - Lanyau, Tonny Anak

AU - Brayon, Fedrick Charlie Matthew

AU - K.P. Kunchi Mohamed, Faizal

AU - Saad, Mohamad Fauzi

AU - Ismail, Ahmad Razali

AU - Abu, Mohamad Puad Haji

PY - 2014

Y1 - 2014

N2 - As a consequence of the accident at the Fukushima Dai-ichi Nuclear Power Plant in Japan, the safety aspects of the one and only research reactor (31 years old) in Malaysia need be reviewed. Based on this decision, Malaysian Nuclear Agency in collaboration with Atomic Energy Licensing Board and Universiti Kebangsaan Malaysia develop a Level-1 Probability Safety Assessment on this research reactor. This work is aimed to evaluate the potential risks of incidents in RTP and at the same time to identify internal and external hazard that may cause any extreme initiating events. This report documents the methodology in developing a Level 1 PSA performed for the RTP as a complementary approach to deterministic safety analysis both in neutronics and thermal hydraulics. This Level-1 PSA work has been performed according to the procedures suggested in relevant IAEA publications and at the same time numbers of procedures has been developed as part of an Integrated Management System programme implemented in Nuclear Malaysia.

AB - As a consequence of the accident at the Fukushima Dai-ichi Nuclear Power Plant in Japan, the safety aspects of the one and only research reactor (31 years old) in Malaysia need be reviewed. Based on this decision, Malaysian Nuclear Agency in collaboration with Atomic Energy Licensing Board and Universiti Kebangsaan Malaysia develop a Level-1 Probability Safety Assessment on this research reactor. This work is aimed to evaluate the potential risks of incidents in RTP and at the same time to identify internal and external hazard that may cause any extreme initiating events. This report documents the methodology in developing a Level 1 PSA performed for the RTP as a complementary approach to deterministic safety analysis both in neutronics and thermal hydraulics. This Level-1 PSA work has been performed according to the procedures suggested in relevant IAEA publications and at the same time numbers of procedures has been developed as part of an Integrated Management System programme implemented in Nuclear Malaysia.

KW - probability safety assessment

KW - psa

KW - research reactor

KW - RTP

KW - TRIGA

UR - http://www.scopus.com/inward/record.url?scp=84906738075&partnerID=8YFLogxK

UR - http://www.scopus.com/inward/citedby.url?scp=84906738075&partnerID=8YFLogxK

U2 - 10.1063/1.4866138

DO - 10.1063/1.4866138

M3 - Conference contribution

SN - 9780735412163

VL - 1584

SP - 240

EP - 244

BT - AIP Conference Proceedings

PB - American Institute of Physics Inc.

ER -