[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] The PUSPATI TRIGA Reactor Simulator was developed in 2012 purposely for 3V program. It is an interactive tool for students understand how to operate the PUSPATI TRIGA Reactor. Students can feeling and understand how to operate the reactor from start-up to shut-down in manual mode of operation. Movement of control rod and reactor parameters are displaying in interactively. Behavior and characteristic for reactor console and reactor itself can be evaluated and understand. Implementation of human system interface is using computer screens, keyboard and mouse. LabVIEW software are using for user interface and mathematical calculation. Polynomial equation based on control rods calibration data as well as operation parameters record was used to calculate and estimated reactor console parameters. The capabilities in user interface, reactor physics and thermal-hydraulics can be expanded and explored to simulation as well as modeling for New Reactor Console, Research Reactor and Nuclear Power Plant. (author)

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[en] Due to aging degradation mechanism, the physical condition of the RTP Fuel cladding surface should be monitored closely. The conventional image record did not have details on the physically changed appearance dimension such as the length, height, coloring and pattern of the effected zone at the fuel cladding surface. Development of this Image processing system will enable us to improve on characterization of our fuel element. (author)

[en] The scope for this research paper is to produce a detail design for Development of Automated Controller System for Controlling Reactivity by using FPGA in Research Reactor Application for high safety nuclear operation. The development of this project including design, purchasing, fabrication, installation, testing and validation and verification for one prototype automated controller system for controlling reactivity in industry local technology for human capacity and capability development towards the first Nuclear Power Programme (NPP) in Malaysia. The specific objectives of this research paper are to Development of Automated Controller System for Controlling Reactivity (ACSCR) in Research Reactor Application (PUSPATI TRIGA Reactor) by using simultaneous movement method; To design, fabricate and produce the accuracy of Control Rods Drive Mechanism to 0.1 mm resolution using a stepper motor as an actuator; To design, install and produce the system response to be more faster by using Field Programmable Gate Array (FPGA) and High Speed Computer; and to improve the Safety Level of the Research Reactor in high safety nuclear operation condition. (author)

[en] The Reactor TRIGA PUSPATI (RTP), Malaysia was installed in the year 1982. The control rod mechanism is very important in reactor operation meaning to control reactivity or neutron production in the reactor. It has four control rods. The current control rods movements are by sequential means one control rod is move at one time. A new control algorithm for Power Controller Simulation has been developing to control the movement of the control rods with uniformly and orderly. By using the Gradient Method which is mathematical expression for the coupling between neutronics and thermal-hydraulics that is considered as the structure of a RTP model of the system. Purpose of the modeling is to reproduce the dynamic behavior of the reactor on the entire operating power range (1 MW). A zero dimensional approach is accounted for and the coupling between neutronics and thermal-hydraulics in natural circulation is considered. The model has been validated through comparison with experimental data, concerning different power transients. For neutronics, point reactor kinetics model with multiple energy group and six delayed neutron precursors group has been adopted. The system reactivity can be modified moving the control rods, which allows the reactor to operate at different power levels. As far as thermal-hydraulics is concerned, two regions have been defined, for example the fuel and the coolant. Heat exchange (convective and conductive) has been modeled by proper adoption of a global heat transfer coefficient. This has been considered as a function of coolant mass flow rate through the core to introduce the effects of force natural cooling (using pump during operation), neutronics and thermal-hydraulics are coupled together by means of fuel and moderator temperature feedback coefficients. The large thermal inertia due to the mass of water in the tank containing the reactor core causes temperature variation during transient to be very small. Therefore, moderator temperature feedback coefficient strongly influences the dynamic behavior of the system and has been estimated making a best-fit between the model response and the experimental data regarding positive reactivity insertion in the system at difference power levels. The results obtained show the reactor powers, reactivity, period, control rods positions, fuel and coolant temperature. The nonlinear system of 11 coupled ODE has been solved by means of Simulink (The MathWorks, Inc. R2010a), which represented a reliable tool for dynamic and control analysis. The model reproduces the real behavior of the system in a very satisfying way. (author)

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[en] V and PL is one of the importance modules in Reactor Protection System (RPS). In Nuclear power plant, V and PL submodules output is high when any two in put off our inputs are high. This paper design and simulate V and PL submodules using LT spice IV software. N-channel Metal Oxide Semiconductor(NMOS) and p-channel Metal Oxide Semiconductor (PMOS) were used to design Complementary Metal Oxide Semiconductor (CMOS) gated. Thus all the gated was applied to design V and PL submodules. This design concept practiced bottom up design rule. At the end, this V and PL function correctly as expected. (author)