[en] The Multi-purpose Experimental Testing Facility (M-PETF) was designed to demonstrate and find solutions to the ageing effects in the RTP structures, systems and components (SSCs). It might be cumbersome if not detected early, leading to severe problems if not verified. The M-PETF is a scaled-down facility that best reflects the RTP and can probe the SSCs' issues. The technical drawing was built using CAD software to visualize the engineering concept of the M-PETF. The difficulty level of the technical drawing was moderate because all sizes needed to be reduced using the available layout to correspond to the space provided. The actual development of M-PETF is expected based on the technical drawings that have been built and verified. This paper highlights the engineering aspects of the M-PETF. (author)

[en] Full-text:PUSPATI TRIGA Reactor (RTP) operated for 41 years and have intention to keep the reactor in operation as long as technically feasible. The preconditions of the long-term operation are the safety and reactor in good condition. In the paper, the review of ageing management covers the structures, systems and components (SSCs). Key elements of ageing management are identified and described. Proper level of understanding of the ageing phenomena is reached and adequate ageing management programmes. The practice and solution of identified ageing management issues will ensure the safety of long-term operation of RTP. (author)

[en] A Multi-Purpose Experimental Test Facility (M-PETF) is currently under development to simulate and test RTP cooling system performance. This scaled-down facility best reflects the actual RTP primary cooling system. The desired profile of the primary cooling system was simulated numerically using computed fluid dynamics with the following setup. The primary coolant tank is scaled down to occupy a 1:4 water cavity. The tank is filled with light water, H₂O to represent the RTP pool water tank. The heat produced by the heaters immersed in the tank behaves according to the amount of heat deposited in the water domain. This study asserts on predicting flow behaviour inside the primary coolant tank. The flow patterns, temperature, and pressure distribution were simulated as the blind benchmark before the experiment was conducted. (author)

[en] Cooling system which consist of numerous pipelines network poses significant problems including in a nuclear reactor. Thermal and irradiation activities, corrosion, embrittlement mechanism as well as aging, provide an environment susceptible to increased pipe failure rates (PFR).The occurrence of PFR is mostly due to aging mechanism including (a) thermal embrittlement, (b) low and high cycle thermal fatigue, (c) stress corrosion cracking mechanisms, and (d) Flow Accelerated Corrosion (FAC) as well as high cycle mechanical fatigue that causing loss of material toughness. Concerning possible accidents due to unreliable pipe integrity, a study on parameters involved in evaluating PFR needs to be developed. However, in assessing PFR, an experiment on a real plant is impossible due to safety issues. Thus, this paper aims to design an experimental test rig by simplifying the primary piping system in reactor TRIGA PUSPATI (RTP). Three alternatives of conceptual design option have been proposed. Methodology in simplifying and designing the test rig is explained briefly in this paper. Finally, a combined design concept of the test rig has been produced based on pre-determined design requirements and presented in this paper. This experimental test rig will be used extensively in generating a comprehensive database which will be used to predict PFR models. (author)

[en] Decommissioning is a process to allow removal of some or all regulatory control that apply to a nuclear site whilst securing the long-term safety of the public and the environment. This process includes the activities release of valuable assets such as site and buildings for unrestricted alternative use, recycling and reuse of materials, restoration of environmental amenity and remediation of the site. This paper will review the decommissioning options, overview decommissioning activities around the world and current status of RTP after 37 years of operation. (author)

[en] Full text: A Molten Salt Reactor (MSR) is unique in its characteristics that offer safer operation, deliver efficient power output that can assure in the sustainable energy production without CO_2 emissions. Several concepts of this kind of reactor have been proposed by stake holder with different design and configuration and up to date they are exasperating to obtain an optimum workable solution to the fuel salt composition in the foresee of neutronic properties, operating temperature, actinide and fission products solubility, chemical control and processing, materials compatibility and handling of waste. Hence, these key issues are wide open as the potential Research and Development in the specific areas of studies. In addition to that, concern arise in the viewpoint of socioeconomic, politics, public acceptance, safety and security, proven technology, proliferation resistance and physical protection that also need to give special attention in problem solving. The worldwide collaboration through Gen IV International Forum has discussed the potential of MSR and addresses on the issues globally. Recently, Malaysia has taken an initiative aiming to participate in MSR studies due to its potential as an energy source using thorium. Therefore, this paper is focusing on the technology assessment for Thorium-breeding Molten Salt Reactor (TMSR) especially on the ability of utilizing thorium as fuel. This assessment also will help to enhance the understanding of thorium beneficiation to cater for the energy demand. (author)

[en] Interstitials and their cluster such as dislocation loops are dispersed in the iron matrix by ion irradiation. In this study, the transmission electron microscopy (TEM) technique is used to analyze the evolution of dislocation loops in Fe-based alloy after irradiation with Fe ion. Thus, in TEM image, g.b = 0 criterion was used for counting the loops and calculating their density. In the nature of the loops, the Burgers vector of a dislocation loop is parallel to the normal vector of the plane containing the dislocation loop. Thus, assuming the dislocation loop is circular, the loop will appear circular, elliptical, or linear, depending on the direction of incidence of the beam. (author)

[en] Computer-Aided Design (CAD) is a very useful tool in design and geometrical modelling for structures, systems, and components (SSCs). The application of CAD enables engineers or designers to visualize their ideal in three?dimensional (3-D) perspective. The CAD is applicable during design, installation, and commissioning phase of the SSCs. The advantages and modern features of CAD software ease the project management throughout the entire project development period. Besides the practicality in the design and development process, the CAD also useful for re-modelling the existing SSCs by converting conventional technical drawing in 2-dimensional (2-D) to more robust 3-D geometry. The rapid development of CAD software worldwide brings additional features such as essential structural analysis and simulation which are very convenient to be used compared to the conventional method. Adaption of CAD at Reaktor TRIGA PUSPATI (RTP) contributes to a wide area of applications. The huge number of SSCs at RTP demands a proper system for managing, updating, and storing valuable technical documents including technical drawings. Effort on the establishment of the directory for CAD at RTP has been started and continuously updated to ensure the information on technical design, analysis, operation, maintenance to decommissioning of the SCCs are kept comprehensively. This paper laid the application of the CAD at the RTP as a part of the important knowledge management aspect. (author)

[en] RTP cooling system was designed to provide sufficient cooling to the reactor core. Heat generated in the reactor core were carried by the primary cooling system to the secondary cooling system through the heat exchangers as a transfer medium. The performance of primary and secondary cooling system in different operation condition; start-up, steady state and shutdown were characterized and evaluated. The characterization of operational parameter has been done at nominal power level in normal operation. The aims of this study are to evaluate the response of the primary and secondary cooling system in start-up, steady state and shutdown condition and to determine the nominal range of parameters at each operating condition. (author)

[en] Power calibration is one of the important aspect for safe operation of the reactor. In RTP, the calorimetric method has been applied in reactor power calibration. This method involves measurement of water temperature in the RTP tank. Water volume and location of the temperature measurement may play an important role to the accuracy of the measurement. In this study, the analysis of water volume changes and thermocouple location effect to the power calibration accuracy has been done. The changes of the water volume are controlled by the variation of water level in reactor tank. The water level is measured by the ultrasonic measurement device. Temperature measurement has been done by thermocouple placed at three different locations. The accuracy of the temperature trend from various condition of measurement has been determined and discussed in this paper. (paper)