Building competence for safety assessment of nuclear installations

Applying IAEA's safety guide for the development of a level 1 probabilistic safety assessment for the TRIGA research reactor in Malaysia

F. C. Brayon, M. Mazleha, P. Prak Tom, A. H.S. Mohd Sarif, Z. Ramli, F. Zakaria, Faizal K.P. Kunchi Mohamed, Abid Aslam, A. Lyubarskiy, I. Kuzmina, P. Hughes, A. Ulses

Research output: Contribution to conferencePaper

1 Citation (Scopus)

Abstract

In 2010, the International Atomic Energy Agency (IAEA) published its Safety Guide on Development and Application of Level 1 Probabilistic Safety Assessment for Nuclear Power Plants (i.e. SSG-3). Although it was aimed at covering state-of-the-art recommendations for the development of PSA of Nuclear Power Plants (NPP), the guidance was deemed to be applicable to other nuclear installations as well. In order to get insights regarding the applicability of SSG-3 for a research reactor, and at the same time to achieve the goal of building competence and capacity for PSA in Malaysia, in December 2012, the IAEA started an extra budgetary project entitled "Applying PSA to Existing Facilities to Develop Transferable Skills in the Use of PSA to Evaluate NPP Safety." This project has been funded by Norway. The facility selected for the PSA study was the TRIGA Puspati Research Reactor (1 MW) which has been in operation in Malaysia since 1982. All major PSA tasks have been performed in accordance with the recommendations provided in SSG-3 (e.g. initiating events analysis, systems analysis, component data evaluation, human reliability analysis, etc). The design specifics of the research reactor under consideration have been addressed in the PSA model (e.g. four end states have been defined, detailed consideration of initiating events induced by human errors, several operational states, etc.). The paper provides an overview of the methodology applied and discusses specific features of PSA tasks for the research reactor. Preliminary results and insights obtained are presented. In addition, insights for guidance in developing a research reactor PSA are highlighted in the paper.

Original languageEnglish
Publication statusPublished - 1 Jan 2014
Event12th International Probabilistic Safety Assessment and Management Conference, PSAM 2014 - Honolulu, United States
Duration: 22 Jun 201427 Jun 2014

Conference

Conference12th International Probabilistic Safety Assessment and Management Conference, PSAM 2014
CountryUnited States
CityHonolulu
Period22/6/1427/6/14

Fingerprint

Research reactors
Nuclear power plants
Nuclear energy
Reliability analysis
Systems analysis

Keywords

  • IAEA SSG-3
  • PSA
  • Research reactor
  • TRIGA

ASJC Scopus subject areas

  • Safety, Risk, Reliability and Quality

Cite this

Brayon, F. C., Mazleha, M., Prak Tom, P., Mohd Sarif, A. H. S., Ramli, Z., Zakaria, F., ... Ulses, A. (2014). Building competence for safety assessment of nuclear installations: Applying IAEA's safety guide for the development of a level 1 probabilistic safety assessment for the TRIGA research reactor in Malaysia. Paper presented at 12th International Probabilistic Safety Assessment and Management Conference, PSAM 2014, Honolulu, United States.

Building competence for safety assessment of nuclear installations : Applying IAEA's safety guide for the development of a level 1 probabilistic safety assessment for the TRIGA research reactor in Malaysia. / Brayon, F. C.; Mazleha, M.; Prak Tom, P.; Mohd Sarif, A. H.S.; Ramli, Z.; Zakaria, F.; K.P. Kunchi Mohamed, Faizal; Aslam, Abid; Lyubarskiy, A.; Kuzmina, I.; Hughes, P.; Ulses, A.

2014. Paper presented at 12th International Probabilistic Safety Assessment and Management Conference, PSAM 2014, Honolulu, United States.

Research output: Contribution to conferencePaper

Brayon, FC, Mazleha, M, Prak Tom, P, Mohd Sarif, AHS, Ramli, Z, Zakaria, F, K.P. Kunchi Mohamed, F, Aslam, A, Lyubarskiy, A, Kuzmina, I, Hughes, P & Ulses, A 2014, 'Building competence for safety assessment of nuclear installations: Applying IAEA's safety guide for the development of a level 1 probabilistic safety assessment for the TRIGA research reactor in Malaysia' Paper presented at 12th International Probabilistic Safety Assessment and Management Conference, PSAM 2014, Honolulu, United States, 22/6/14 - 27/6/14, .
Brayon FC, Mazleha M, Prak Tom P, Mohd Sarif AHS, Ramli Z, Zakaria F et al. Building competence for safety assessment of nuclear installations: Applying IAEA's safety guide for the development of a level 1 probabilistic safety assessment for the TRIGA research reactor in Malaysia. 2014. Paper presented at 12th International Probabilistic Safety Assessment and Management Conference, PSAM 2014, Honolulu, United States.
Brayon, F. C. ; Mazleha, M. ; Prak Tom, P. ; Mohd Sarif, A. H.S. ; Ramli, Z. ; Zakaria, F. ; K.P. Kunchi Mohamed, Faizal ; Aslam, Abid ; Lyubarskiy, A. ; Kuzmina, I. ; Hughes, P. ; Ulses, A. / Building competence for safety assessment of nuclear installations : Applying IAEA's safety guide for the development of a level 1 probabilistic safety assessment for the TRIGA research reactor in Malaysia. Paper presented at 12th International Probabilistic Safety Assessment and Management Conference, PSAM 2014, Honolulu, United States.
@conference{5eb8c9552daf466aac4a03b16d74b8d3,
title = "Building competence for safety assessment of nuclear installations: Applying IAEA's safety guide for the development of a level 1 probabilistic safety assessment for the TRIGA research reactor in Malaysia",
abstract = "In 2010, the International Atomic Energy Agency (IAEA) published its Safety Guide on Development and Application of Level 1 Probabilistic Safety Assessment for Nuclear Power Plants (i.e. SSG-3). Although it was aimed at covering state-of-the-art recommendations for the development of PSA of Nuclear Power Plants (NPP), the guidance was deemed to be applicable to other nuclear installations as well. In order to get insights regarding the applicability of SSG-3 for a research reactor, and at the same time to achieve the goal of building competence and capacity for PSA in Malaysia, in December 2012, the IAEA started an extra budgetary project entitled {"}Applying PSA to Existing Facilities to Develop Transferable Skills in the Use of PSA to Evaluate NPP Safety.{"} This project has been funded by Norway. The facility selected for the PSA study was the TRIGA Puspati Research Reactor (1 MW) which has been in operation in Malaysia since 1982. All major PSA tasks have been performed in accordance with the recommendations provided in SSG-3 (e.g. initiating events analysis, systems analysis, component data evaluation, human reliability analysis, etc). The design specifics of the research reactor under consideration have been addressed in the PSA model (e.g. four end states have been defined, detailed consideration of initiating events induced by human errors, several operational states, etc.). The paper provides an overview of the methodology applied and discusses specific features of PSA tasks for the research reactor. Preliminary results and insights obtained are presented. In addition, insights for guidance in developing a research reactor PSA are highlighted in the paper.",
keywords = "IAEA SSG-3, PSA, Research reactor, TRIGA",
author = "Brayon, {F. C.} and M. Mazleha and {Prak Tom}, P. and {Mohd Sarif}, {A. H.S.} and Z. Ramli and F. Zakaria and {K.P. Kunchi Mohamed}, Faizal and Abid Aslam and A. Lyubarskiy and I. Kuzmina and P. Hughes and A. Ulses",
year = "2014",
month = "1",
day = "1",
language = "English",
note = "12th International Probabilistic Safety Assessment and Management Conference, PSAM 2014 ; Conference date: 22-06-2014 Through 27-06-2014",

}

TY - CONF

T1 - Building competence for safety assessment of nuclear installations

T2 - Applying IAEA's safety guide for the development of a level 1 probabilistic safety assessment for the TRIGA research reactor in Malaysia

AU - Brayon, F. C.

AU - Mazleha, M.

AU - Prak Tom, P.

AU - Mohd Sarif, A. H.S.

AU - Ramli, Z.

AU - Zakaria, F.

AU - K.P. Kunchi Mohamed, Faizal

AU - Aslam, Abid

AU - Lyubarskiy, A.

AU - Kuzmina, I.

AU - Hughes, P.

AU - Ulses, A.

PY - 2014/1/1

Y1 - 2014/1/1

N2 - In 2010, the International Atomic Energy Agency (IAEA) published its Safety Guide on Development and Application of Level 1 Probabilistic Safety Assessment for Nuclear Power Plants (i.e. SSG-3). Although it was aimed at covering state-of-the-art recommendations for the development of PSA of Nuclear Power Plants (NPP), the guidance was deemed to be applicable to other nuclear installations as well. In order to get insights regarding the applicability of SSG-3 for a research reactor, and at the same time to achieve the goal of building competence and capacity for PSA in Malaysia, in December 2012, the IAEA started an extra budgetary project entitled "Applying PSA to Existing Facilities to Develop Transferable Skills in the Use of PSA to Evaluate NPP Safety." This project has been funded by Norway. The facility selected for the PSA study was the TRIGA Puspati Research Reactor (1 MW) which has been in operation in Malaysia since 1982. All major PSA tasks have been performed in accordance with the recommendations provided in SSG-3 (e.g. initiating events analysis, systems analysis, component data evaluation, human reliability analysis, etc). The design specifics of the research reactor under consideration have been addressed in the PSA model (e.g. four end states have been defined, detailed consideration of initiating events induced by human errors, several operational states, etc.). The paper provides an overview of the methodology applied and discusses specific features of PSA tasks for the research reactor. Preliminary results and insights obtained are presented. In addition, insights for guidance in developing a research reactor PSA are highlighted in the paper.

AB - In 2010, the International Atomic Energy Agency (IAEA) published its Safety Guide on Development and Application of Level 1 Probabilistic Safety Assessment for Nuclear Power Plants (i.e. SSG-3). Although it was aimed at covering state-of-the-art recommendations for the development of PSA of Nuclear Power Plants (NPP), the guidance was deemed to be applicable to other nuclear installations as well. In order to get insights regarding the applicability of SSG-3 for a research reactor, and at the same time to achieve the goal of building competence and capacity for PSA in Malaysia, in December 2012, the IAEA started an extra budgetary project entitled "Applying PSA to Existing Facilities to Develop Transferable Skills in the Use of PSA to Evaluate NPP Safety." This project has been funded by Norway. The facility selected for the PSA study was the TRIGA Puspati Research Reactor (1 MW) which has been in operation in Malaysia since 1982. All major PSA tasks have been performed in accordance with the recommendations provided in SSG-3 (e.g. initiating events analysis, systems analysis, component data evaluation, human reliability analysis, etc). The design specifics of the research reactor under consideration have been addressed in the PSA model (e.g. four end states have been defined, detailed consideration of initiating events induced by human errors, several operational states, etc.). The paper provides an overview of the methodology applied and discusses specific features of PSA tasks for the research reactor. Preliminary results and insights obtained are presented. In addition, insights for guidance in developing a research reactor PSA are highlighted in the paper.

KW - IAEA SSG-3

KW - PSA

KW - Research reactor

KW - TRIGA

UR - http://www.scopus.com/inward/record.url?scp=85066671530&partnerID=8YFLogxK

UR - http://www.scopus.com/inward/citedby.url?scp=85066671530&partnerID=8YFLogxK

M3 - Paper

ER -