[en] An assessment of airborne release at PUSPATI TRIGA Reactor (RTP) exhaust stack was conducted. Radioactive gases continuously released and monitored from exhaust stack while RTP is in operation using Stack Monitoring System (SMS). The importance of having SMS are to: (1) monitor level of releases for protection of plant personnel; (2) monitor the air in the reactor building structure; (3) detect leakage from the reactor systems; and (4) control ventilation when the radioactivity level has exceeded a defined threshold. The system monitored gross radioactive particulate, iodine and noble gases and activated an alarm when the observed concentration exceeded a threshold value. However, these continuous measurements should be supported with analysis of samples from the release to obtain quantitative radionuclide concentrations in the effluent stream and as part of assurance to the current SMS. Therefore, the purpose of this paper is to determine; (1) the total activity concentration of radioactive particulate; and (2) radioiodine trapped on the filters. In assessing the release of radioactive concentration, two independent approaches used. The first approach is measuring the sample (for example radioactive trapped on filters) at point discharge exhaust stack from the current SMS. Meanwhile, the other approach is measuring the sample from release at several locations around the RTP by using independent air sampler. The concentration level of radioactivity present in the samples was counted using a gamma spectrometer based on the energy and intensity of the emitted gamma. The result showed that the amount of radioactive material of particulate and radioiodine is in the range of minimum detectable peak areas (below 1.0 Bq/ m³). All the measurements performed in this paper were far below the release limit stipulated in the RTP Safety Analysis Report (SAR). (author)

[en] Ageing management is one of the important safety factors to be implemented pro actively throughout the lifetime of a research reactor. In order to continue the safe operation of a research reactor from the reactor safety standpoint, a systematic and methodical approach should be taken. In practice, ageing management programme is accomplished by integrating the existing programmes including maintenance, periodic testing and inspection and periodic safety reviews. Such approach will be a good platform for the reactor operation and maintenance group to utilize data from existing maintenance programme to be incorporate into the ageing maintenance system. This paper will describe the ageing management programme for Reactor TRIGA PUSPATI (RTP). (Author)

[en] Primary cooling system consists of pumps, heat exchangers, probes, a nitrogen-16 diffuser and associated valves is connected to the reactor TRIGA PUSPATI (RTP) tank by aluminium pipes. Both the primary cooling system and the reactor tank is filled with demineralized light water (H₂O), which serves as a coolant, moderator as well as shielding. During reactor operation, vaporization in the reactor tank will reduce the primary water and contribute to the formation of vapor in the reactor hall. The vaporization may influence the function of the water subsequently may affect the safety of the reactor operation. It is essential to know the vaporization rate of the primary water to ensure its functionality. This paper will present the vaporization rate of the primary cooling water from the reactor tank and the influence of temperature of the water in the reactor tank to the vaporization rate. (author)

No abstract available

[en] The 1 MW PUSPATI TRIGA Reactor (RTP), located at Malaysian Nuclear Agency has been operated since its first criticality on 28 June 1982. The RTP uses uranium zirconium hydride fuel enriched to about 20% of U-235. The RTP has four control rods made up of boron carbide where three are fuel-followers and one is an air-follower. The aluminium cylindrical core can accommodate up to 127 fuel elements while the reflector surrounding it is made from high purity graphite. Since, the reactor power is relatively small, natural convection is used for cooling. Light water is used both as a coolant and as well as a moderator. Visual inspection of the core, fuel and control rods are carried out routinely to ascertain their integrity. An underwater camera and boroscope was used to visually inspect the top grid plate of the core as well as the control rods. No visible defect was detected at the top grid plate however, two of the fuel-follower control rods had blemishes on its surface. This paper will describe the findings of the visual inspection as well as corrective actions taken. (author)

[en] Reactor Triga PUSPATI (RTP) has been operated since 1982 till now. For such long period, the organization feels the need to upgrade the power from 1 MW to 3 MW which involved changing new fuels. Spent fuels will be stored in a Spent Fuel Pool. The process of transferring spent fuels into Spent Fuels Pool required a fuel transfer cask. This paper discussed the design concept for the fuel transfer cast which is essential equipment for reactor upgrading mission. (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] 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] The PUSPATI TRIGA reactor (RTP) reached its first criticality status on 28 June 1982 with an installed capacity of 1 MW. After 26 years in operation, the ageing process has set in and many systems in the reactor need maintenance and replacement. Among these systems, the more critical one is the heat exchanger system. Currently, the shell and tube type heat exchanger is being used. It has been observed that the performance of the heat exchanger has dropped significantly over the years. Visual inspections indicate that the tubes are corroded or even to the extent of being totally blocked. With this in mind and also with the setting up of the new Nuclear Power Division, whose mission includes upgrading the present reactor to 3 MW, the heat exchanger system is essential and a critical component. Literature indicates that the use of plate type exchangers are more efficient than the current shell and tube type. This paper will look into the engineering and safety aspects of using the plate type heat exchanger to the current TRIGA PUSPATI reactor. (Author)

No abstract available