Nuclear Reactor Safety

(Reactor Technology Assessment, Engineering and Safety Section (TES))

OBJECTIVES

• Undertake task and build expertise on technology assessment towards type of research and power reactors as well as any related technical-aspect support for the development of nuclear power reactor in the country.
• Build capacity and expertise as well as support the engineering aspects of the RTP as part of preparations towards the development of nuclear energy in Malaysia.
• Build capacity and expertise in the field of research and power reactors safety part of the preparations towards the development of nuclear energy in Malaysia as well as in ensuring safe operations and utilization of the research reactor.
  
  

 

SCOPE

1. Reactor Technology Assessment
   
   Nuclear power reactor, Pressurized Water Reactors, Boiling Water Reactors, Heavy Water-Moderated Pressure Tube Reactors, Graphite-Moderated Pressure Tube Reactors, Graphite Moderated Gas-cooled Reactors, Liquid-Metal Fast Breeder Reactors, Advanced Reactors, Research Reactors.


2. Reactor Engineering
   
   Design and analysis of thermal hydraulics and thermodynamics, safety engineering, building, shielding, ECCS, earthquake and structure, siting parameters, electrical design of nuclear power plants (NPP), design of research and radiation facility.


3. Reactor safety
   
   Review and update the existing safety analysis report (SAR), development of SAR for new reactors, reactor safety assessment, prediction of Postulated Initiating Events (PIE) through assessment, Probabilistic Safety Assessment (PSA), Deterministic Safety Assessment (DSA) for accident analysis, carry out reactor safety assessments.

 

 

Activities

Research

• RTP 3000 Thermal Hydraulic Calculations using the codes Coolod-N2 and PARET for the arrangement in the core, EUREKA and RELAP 5 for the entire RTP system.
• Pre-SAR development for the RTP300
• To conduct reactor technology assessment

 

Project

• Upgrade RTP, the calculation of "Thermal Hydraulics" for the core and the whole system, RTP
• Assist in the design concept of "fuel transfer cask" and "spent fuel pond."
• Assist in the commissioning of RTP primary cooling system.
• To assist in the examination of the reactor tank using ultra sonic sensor defects (ultrasonic flaw Detector)
• To update the Safety Analysis Report (SAR) for RTP

 

Services

• Reactor Operator course
• Briefings to RTP Visitors
• Trainers in the field of "thermal hydraulic" and reactor safety
• Served at Radiological Emergency Centre (REC), AELB
  

 

Products

• Thermal Hydraulics design proposals for upgrading the reactor project.

 

Publications

International Seminar Papers / Kertas Seminar Antarabangsa

·   Mazleha Maskin and Kwong Sik Choi. Lessons Learned in Preparation and Review of Safety Analysis Report of PUSPATI TRIGA Reactor in Malaysia. KNS Spring Conference. May 27-28 2010, Gangwondo, South Korea.

 

National Seminar Paper / Kertas Seminar Kebangsaan

·   Mohd Fairus Abdul Farid, Julia Abdul Karim, and Mohammad Suhaimi Kassim.
Steady State Thermal Hydraulic Calculation for PUSPATI TRIGA Reactor Using COOLOD-N2. Proceedings Nuclear Science, Technology and Engineering Conference (NUSTEC).August 4-5, 2010. Serdang, Malaysia

·   Tonny Anak Lanyau, Mohd Fazli Zakaria, Zaredah Hashim, Mohd Fairus Abdul Farid and Mohammad Suhaimi Kassim. Replacement of PUSPATI TRIGA Reactor Primary Cooling System and Safety Considerations. Proceedings Nuclear Science, Technology and Engineering Conference (NUSTEC).August 4-5, 2010. Serdang, Malaysia

·   Tonny Lanyau, Mohd Fazli Zakaria, Zaredah Hashim, Ahmad Nabil Ab Rahim and Mohammad Suhaimi Kassim. Conceptual Design of PUSPATI TRIGA Reactor Spent Fuel Storage Rack. Proceedings of the Nuclear Malaysia R&D Seminar 2010. October 12-15, 2010. Bangi, Malaysia

·   Zaredah, H., Faridah, M.T., Maznah, A.M. and Nabil, M.M.. Application of Combined Heat and Power in Malaysia Industrial Sector.  Proceedings of the Nuclear Malaysia R&D Seminar 2010. October 12-15, 2010. Bangi, Malaysia

·   Zaredah, H., Mohd Fairus, A.F., Lanyau, T., Syahirah, A.R., Mohd Fazli, Z., Ariff Shah, I. and Mohamad Suhaimi, K.. Thermal Hydraulic Parameter Studies of Heat Exchanger for the PUSPATI Research Reactor. Proceedings of the Nuclear Malaysia R&D Seminar 2010. October 12-15, 2010. Bangi, Malaysia

·   Zakaria, M.F., Lanyau, T. and Kassim, M. S..Commissioning of PUSPATI TRIGA Reactor Primary Cooling System and Lessons Learnt. Proceedings Nuclear Science, Technology and Engineering Conference (NUSTEC).August 4-5, 2010. Serdang, Malaysia

·   Khaironie M.T., Mohd Fairus A.F., Zareen Khan A.J.K., Mohd Zaid, M. and Muhammad Khairul Ariff, M..Techno Economic Assessment for Upgrading PUSPATI TRIGA Research Reactor: Issues, Challenges and Findings. Proceedings Nuclear Science, Technology and Engineering Conference (NUSTEC).August 4-5, 2010. Serdang, Malaysia

·   Zakaria, M.F., Lanyau, T. and Ab Rahim, A. N.. Reactor TRIGA PUSPATI Spent Fuel Pool Conceptual Design. Proceedings of the Nuclear Malaysia R&D Seminar 2010. October 12-15, 2010. Bangi, Malaysia

·   Ab Rahim, A.N., Ramli, N., Lanyau, T., Prak Tom, P. and Zakaria, M.F.. Fuel Transfer Cask Design Concept for Reactor TRIGA PUSPATI. Proceedings of the Nuclear Malaysia R&D Seminar 2010. October 12-15, 2010. Bangi, Malaysia

·   Phongsakorn Prak Tom, Tonny Anak Lanyau, Ahmad Nabil Ab Rahim, Yusof Abdullah. Study of Radiography and Hardness of Aluminum 6061-T6 Pipe Used in Primary Cooling System of PUSPATI TRIGA Reactor. Proceedings of the Nuclear Malaysia R&D Seminar 2010. October 12-15, 2010. Bangi, Malaysia

 

Country Report / Penerbitan Umum

·   Mohammad Suhaimi Kassim, Mohd Fairus Abdul Farid, Khairol Nizam Mohamed, Mazleha Maskin, Tonny anak Lanyau, Zaredah Hashim and Mohd Huzair Hussain. Initiatives to Support Implementation of Nuclear Power Programme (NPP) Roadmap: Research & Development and Support & Services by TES. Workshop on NPP Implementation with warga BKN. July 12-13, 2010. Bangi, Malaysia.

·   Mohammad Suhaimi Kassim and  Zulkefle Hussin. Status of ISE and Safety Analysis Activities in Malaysia. IAEA ANSN SATG Annual Meeting. October 4-8, 2010. Daejeon, Korea.

·   Kassim, M. S., Klaysubun, N., Toibayev, Z., Doan, L. A. and Kumekawa, H.. Establishing a Safeguards System of Nuclear Material Accounting and Control (NMAC) at a Facility Level. IAEA Regional Training Course on State Systems of Accounting for and Control of Nuclear Materials. October 18-29, 2010. Tokai, Japan.

·   Klaysubun, N., Kassim, M. S., Toibayev, Z., Doan, L. A. and Kumekawa, H.. SSAC at State level. IAEA Regional Training Course on State Systems of Accounting for and Control of Nuclear Materials. October 18-29, 2010. Tokai, Japan.

·   Toibayev, Z., Kassim, M. S., Klaysubun, N., Doan, L. A., Kumekawa, H.. Fuel Design, Storage and Handling. IAEA Regional Training Course on State Systems of Accounting for and Control of Nuclear Materials. October 18-29, 2010. Tokai, Japan.

 

Technical Report

·   Mohammad Suhaimi Kassim, Mohd Fairus Farid, Tonny Lanyau & Zaredah Hashim. Annual Report of Reactor Technology Assessment, Engineering and Safety Section (TES). June 2010. (in Bahasa Malaysia)

 

Publication

International Seminar Paper

Mazleha Maskin and Kwong Sik Choi. Lessons Learned in Preparation and Review of Safety Analysis Report of Puspati TRIGA Reactor in Malaysia. Spring KNS Conference. May 27-28 2010, Gangwondo, South Korea.

Contact persons

No	Name	Grade	Tel. No.
1.	Mr. Mohammad Suhaimi Kassim (Manager)	Q48	1093 / Direct 8928 2950
2.	Mr. Mohd Fairus Abd Farid	Q44	1274
3.	Mrs. Mazleha Maskin	Q44	1734
4.	Mr. Tonny Anak Lanyau	Q41	1847
5.	Mrs. Zaredah Hashim	Q41	1552
6.	Mr. Mohd Huzair Hussain	Q41	1092