[en] A three decade aging PUSPATI TRIGA Reactor will soon require spent fuels to be replaced with fresh fuels. Initial procedure requires these spent fuels be cooled down due to high temperature and high radioactivity resulted from fission products activities and then transferred out of reactor tank into a spent fuel pool. Performing this task will need a fuel transfer cask (FTC) to provide sufficient radiation shielding for the workers during fuels transferring task. Currently the only economically viable route FTC to get into reactor tank is through the top of reactor tank using crane. The huge and high density lead filled FTC will be hanging throughout the task of transferring each fuel element thus FTC is subjected to tensile stress during its operation. Lug component is anticipated to be one of the main weaknesses of FTC design subjected under tensile load due to it diminutive in size but very large amount of stress to be introduced on it. Therefore lugs component requires an adequate stress analysis to prove the design reliability. This paper will discuss the structural strength using conventional engineering calculation based on best estimate approach. (author)

[en] Adequate safety measures and precautions, which follow relevant safety standards and procedures, should be in place so that personnel safety is assured. Nevertheless, the public, visitor, contractor or anyone who wishes to enter or be in the reactor building should be well informed with the safety measures applied. Furthermore, these same elements of safety are also applied to other irradiation facilities within the premises of Nuclear Malaysia. This paper will describes and explains current safety management system being enforced especially in the TRIGA PUSPATI Reactor (RTP) namely radiation monitoring system, safety equipment, safe work instruction, and interconnected internal and external health, safety and security related departments. (author)

[en] RTP tank and core structure has been continuously in contact with water and several parts have been subjected high radiation due to operational demand since 1982. The tank liner is one of the first barriers to keep the RTP primary coolant from leaking out. Currently, limited studies on the changes of the surface condition and thickness of the RTP tank has been discussed. This paper will discuss the previous findings from ultrasonic thickness inspection of the RTP tank wall and borescopes visual inspection of the RTP tank base. (author)

[en] Malaysia is in the stage of conducting Preliminary Technical Feasibility Study for the Deployment of Small Modular Reactor (SMR). There are different types of SMR, some already under construction in Argentina (CAREM) and China (HTR-PM) - (light water reactor and high temperature reactor technologies), others with near-term deployment such as SMART in South Korea, ACP100 in China, mPower and NuScale in the US, and others with longer term deployment prospects (liquid-metal cooled reactor technologies). The study was mainly to get an overview of the technology available in the market. The SMR ranking in the study was done through listing out the most deployable technology in the market according to their types. As a new comer country, the proven technology with an excellent operation history will usually be the main consideration points. (author)

[en] The shielding calculations for RTP fuel transfer cask was performed by using computer code Micro shield 7.02. Micro shield is a computer code designed to provide a model to be used for shielding calculations. The results of the calculations can be obtained fast but the code is not suitable for complex geometries with a shielding composed of more than one material. Nevertheless, the program is sufficient for As Low As Reasonable Achievable (ALARA) optimization calculations. In this calculation, a geometry based on the conceptual design of RTP fuel transfer cask was modeled. Shielding material used in the calculations were lead (Pb) and stainless steel 304 (SS304). The results obtained from these calculations are discussed in this paper. (author)

No abstract available

[en] Full-text:Evaporation Standard Tank (EST) has been designed and developed for evaporation rate measurement at RTP Spent Fuel Pool (SFP). The EST is installed to measure the water loss due to evaporation. The evaporation rate of the water inside the EST is used to estimate the evaporation rate of the spent fuel pool. Several factors that may influence the rate of evaporation have been considered such as ambient temperature, humidity, air flow and location inside the SFP building. Important design criteria to be considered are stability, loading, installation, sizing, material and fabrication limitation. This paper discussed the conceptual design of the EST. (author)

[en] PUSPATI TRIGA Reactor (RTP) has been operating for over 33 years safely. However, for inter operability RTP continue for several decades, the Centre for Nuclear Technology (RTP) has implemented and is planning several projects to realize this. (author)

[en] Reactor TRIGA PUSPATI (RTP) has been operating almost 30 years. Many components are ageing. Nuclear Malaysia has taken an initiative to manage this ageing problem to prolong the life of the reactor. Hence, reactor upgrading project already commence started with the reactor console. To upgrade the core, all the fuel must be taken out from the core. A conceptual design of fuel transfer cask already done. This paper will discuss about the option of safe working procedure for transferring the fuel to the spent fuel pool for temporary. Hence, radiation protection for operator should be considered during the process. (author)

[en] Radiation Monitoring System aiming to limiting dose exposed to personnel to the lowest level referring to the concept of ALARA (As Low As Reasonably Achievable). Atomic Energy Licensing (Basic Safety Radiation Protection) Regulation 2010 (Act 304) is a baseline to control employee and public radiation protection program and guideline, as well as to meet the requirement of the Occupational Safety and Health 1994 (Act 514). (author)