Abstract. Since its first criticality in 1982, PUSPATI TRIGA Reactor (RTP) has been operated for more than 30 years. As RTP become older, ageing problems have been seen to be the prominent issues. In addressing the ageing issues, an Ageing Management (AgeM) database for managing related ageing matters was systematically developed. This paper presents the development of AgeM database taking into account all RTP major Systems, Structures and Components (SSCs) and ageing mechanism of these SSCs through the system surveillance program.
An internal Fire Probabilistic Safety Assessment (FPSA) study was conducted in the control room of the TRIGA PUSPATI (RTP) research reactor. This study aims to determine the likelihood of a fire occurring in the control room of RTP and the probability of fire occurring after an accident loss of instrumentation and control (LOIC) to the core damage frequency (CDF) value. The quantification results of the CDF are compared between LOIC with fire-induced (LOIC-F) and without fire-induced (LOIC). A methodical strategy to identify potential fire hazards that includes the precise identification of the design area, the size of any opening compartments, the location of electrical cabinets and fire suppression systems, as well as the placement of any safety-related equipment was applied. Included is Failure Mode and Effect Analysis (FMEA), which determines failure modes and designates repercussions for each scenario. This research will contribute on providing essential information on status of fire in RTP’s control room as an insight of identifying any risk of fire scenario that may occur including investigation of current fire protection system sufficiency. In addition, a core damage end state of consequences of fire after an LOIC is also presented. The result of this research can be beneficial and creating awareness to the management as well as reactor operators in case of fire in the control room of RTP.
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.
Depth profile of Helium irradiation effects in reactor pressure vessel (RPV) model material is identified using a nano-indentation technique in order to develop a new methodology to clarify the solute-vacancy interaction. 2 MeV He ion was irradiated in pure iron at room temperature with and without an energy degrator. The indentation hardness was measured by nanoindentation changing the load at 9 levels. Hardening in irradiated materials was clearly observed in all indentation loads as well as the well-known indentation size effect. It was interesting that the significant increase of hardness was recognized at 0.8 μm depth, which is corresponding to the obstacle of deformation at 3˜4 μm depth, that would be the cause of helium implantation. Furthermore, dose effects on 3MeV Si irradiated RPV model materials were confirmed.
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