[en] Fuels containment system is a facility to isolate fouled fuels so that their fission product could not contaminate the reactor pool. This system was designed to anticipate the occurrence of the fuels damage by leakage in consequence of burn up process in the reactor core. The proposed design contains two RSG-GAS fouled fuels bundles and could not distribute the fission product to reactor pool. From the analysis result showed that the proposed design is capable to the working stresses and without heat accumulation in the system during its operation

[en] At normal operation of 15 MW prior to shut down, the capability test of 3 unit emergency pool cooling system have been carried out at different time. The system is used to cool the decay heat after reactor shut down at normal operation as well as emergency condition. The systems are operated independently toward the reactor operation and other emergency system. Three cooler systems of reactor pool emergency have capability above requires capability. This paper describes comparison between capability of intake of heat which remain at the commissioning phase and at examination to know the degradation of performance. Capability of intake of heat at the examination, one line system is different from other the system and have degradation compared to capability at the commissioning. Degradation capability is caused by natural process and not caused by encumbering factor. The equipment seldom operated, so the level of degradation is 36.5 % still become safety limit. The degradation equipment does not affect alertness in operating of reactor. (author)

[en] Study for electric power improvement means that discussion for characteristics of electricity focused at the fluctuation of voltage waveforms caused by influence of lightning attack both directly or indirectly to RSG-GAS nuclear installation. The measuring BHA bus bar voltage waveform by used power line monitor will be done at normal conditions (there's no lightning attacks). The measuring result shows that the voltage waveform is sinusoidal. The measuring devices as describe above will be installs for continuous measuring to get voltage waveform in the case of lightning attack occurs. The influence of lightning attack into power line can be read from that device recording which show that the voltage waveform have changed. In order to recovery the voltage waveform can be done by used the lightning arrester, and over voltage arrester that installed at bus bar BHA-02. That device will be hoped could overcome the damage of waveform to normal condition. (author)

[en] Reactor power calibration is the process of adjusting or re-measuring the reactor power measuring tools or channels against standard values. At the time of calibration there is a correction factor which is important in the reactor power calibration that must be measured and analyzed periodically. The current problem is the absence of correction factor measurement of power calibration especially at the operation of reactor at 15 MW and 30 MW. Measurement of correction factor is intended to obtain the shift of correction factor that has been used in the calculation of RSG-GAS reactor power calibration, to know the effect of the change on reactor power calibration, and to know the difference of correction factor value when the secondary coolant is operated with 4 and 7 Unit blower. This paper involves the recording of reactor power calibration, and measuring calibration correction factor at 15 MW and 30 MW power. Correction factor measurements are made under the conditions of the entire system being operated as during high power operation, but the difference is that the reactor is not burdened by power (reactor is not operated). The recording of data is carried out until the temperature difference in and out of the stable terrace with prior initial data recording before the cooling system is operated. From the measurement results obtained a correction factor when the secondary cooling system operated with 4 units of blower (operation 15 MW) is 0.1 °C (previous correction factor is 0.41 °C) and correction factor when the secondary cooling system is operated with 7 units Blower (operation 30 MW) that is 0.12 °C. Changes and differences in correction factors affect the reactor power calibration results. It is expected that the measurement result can be a reference in conducting RSG-GAS reactor power calibration. (author)

[en] The RSG-GAS reactor is a research reactor operated for radioisotope production, neutron activation analysis, research and material testing. The RSG-GAS reactor operates for 625 MWd each cycle and core fuel management uses a 5/1 pattern in the fuel loading. Every fuels replacement in the reactor core performed calculating and measured reactor parameters to determine the safety factor of reactor operation. Under normal operating conditions the irradiation facility is in a water or aluminium dummy. The addition of aluminum dummy to the irradiation facility needs to be known for its effect on the neutronic parameters of the RSG-GAS reactor. In this paper, we evaluated the calculation and measurement of reactor operating parameters and the dummy effect of aluminium on reactivity and neutron flux of 97 RSG-GAS reactors core. The calculation of operating parameters is done using a combination of WIMS/D5 for the cell generation cross section, Batan-2DIFF to calculate reactivity, radial power peacking factor and Batan-3DIFF to calculate the axial power peacking factor and neutron flux in the reactor core. Based on the results of calculations and measurements indicate that the 97 RSG-GAS reactors core meets the reactor operating safety limit. The reactivity effect due to the placement of the aluminium dummy on the CIP 0.17 % Δk/k. If the aluminium dummy is placed in the CIP and the IP will increase the flux in that position because aluminium has a very good moderating power. The value of power factor for peak radial and axial power is 1.2200 and 1.2902, respectively. The value is still within the safety limit of reactor operations. (author)

[en] The RSG GAS reactor in Serpong was stepping the age of 26 years since August 2012. It is of necessary to evaluate the safety of all operational aspects in order to provide adequate data for the decision maker to plan the next operation program especially to guarantee the safe operation until the end of its designed age, and to respond the Regulation of BAPETEN NO. 2/2011, by which request a self safety verification by licensee at least once every 5 years. The aim of the research is to know the performance of safety systems of the RSG GAS reactor comprising nuclear, thermal hydraulics and radiation aspects, during its 25 years operation. Evaluation was done by collecting all operation data in period of 25 years and then compared to the safety limits and conditions of reactor operation. The results showed that during the period the reactor was operated in a safe manner. During normal operations all safety parameters show the values lower than the safety limits. While during incidents or disturbances conditions, the reactor protection system always took actions to shut the reactor down. A number of 27 incidents have taken place but in scale 1 (anomaly) and nol (deviation) of the INES Scale which means no radiological impacts occurred down. A number of 27 incidents have taken place but in scale 1 (anomaly) and nol (deviation) of the INES Scale which means no radiological impacts occurred. (author)

[en] Diesel generator is one of the important components of emergency electrical power supply when the main power supply is disrupted. Unable to operation of diesel engines will have a serious impact to the operation of the reactor. This paper aims to evaluate the cause of disruption of the diesel generator BRV10 at the Multi Purpose Reactor GA Siwabessy occurred in 2014. This event makes enough attention because its cause is deemed unusual. Evaluation is done by investigating the causes of the disorder, do the repair, test functions and anticipate that similar events do not recur in the future. From the results of the evaluation of the causes of disorders known that diesel is a diesel mixing with water and mud that had buried long estimated in the diesel engine fuel tank. Is believed to cause the fuel tank care is less than optimal. (author)

[en] On the technical specification of the SAR RSG-GAS is mentioned that after the lifetime of the absorber or in case of mechanical defect, the fork absorber shall be changed. This mentioned came from other research reactor experience that the change of their absorbers has been carried out after 30.000 MW D operation. Today RSG-GAS has operated up to 30.000 MW D but the fork absorbers is still in used. Base on this need to evaluate the lifetime of fork absorbers to ensure that the fork absorbers still in good condition. With learn the history of the fork absorber operation surround the visual inspection, the rod drop time measurements and the reactivity/safety margin of control rod measurements can be concluded that until the last 50^th operation cycles the mechanical form of fork absorbers are in good condition. The performance as neutrons absorber has degraded about 14%, but the fork absorbers can be used for ± 650 MW D/operation cycles, which it indicated the good value of the excess reactivity and the safety margin of the control rods

[en] The primary coolant water purification system serves to removes the product activation and mechanical impurities from the water in the reactor pool and maintain the quality of primary coolant water. The system consists of ion exchange resin filter (mixed bed ion exchange resin filter) and a mechanical filter (resin trap). Identification of the cause of the pressure increase on the mechanical filter (resin trap) purification system is done by comparing the results of the determination of the chemical elements contained in the sample taken at the time of backwashing the ion exchange resin purification systems and chemical elements contained in the ion exchange resin purification system. Determining the content of chemical elements in the samples was done by SEM-EDAX. The results showed that the determination of chemical elements in the ion exchange resin primary coolant water purification system detected the elements C, O, S and N. whereas in sediment samples taken at the time of backwashing the ion exchange resin purification system detected an element of C, O, S, Al, Si and Fe. It can be said that the two samples have the same type of main elements of the ion exchange resin, so it can be stated that the cause of the increased pressure on mechanical filters (resin trap) primary cooling water purification system of the reactor RSG-GAS is possible because of the chemical degradation of the ion exchange resin caused because of the length of time the use of ion exchange resins, which caught the mechanical filter (resin trap). Thus the duration of use of ion exchange resins affect the mechanical filter (resin trap) replacement. (author)

[en] There has been evaluation of the implementation of Occupational Health and Safety (OHS) targets in 2016. Based on the policy of the Head of National Nuclear Energy Agency which states that Safety is the highest priority, PRSG shall be responsible for the safety generated during the operation and utilization of the RSG-GAS reactor. But in reality individual awareness in implementing OHS is still not consistent. Awareness raising in safety needs to be done by promoting the development of a safety culture both individually and organization on an on going basis. One way to find out how far the implementation of the safety culture of employees in the PRSG then made the goal of OHS in each year, especially in 2016. The current problem is the evaluation of the OHS implementation targets in 2016 in PRSG which has not been done yet. This paper is prepared to evaluate the implementation of the 2016 OHS target consisting of 8 activity review points undertaken in the PRSG. Evaluation Implementation of K3 objectives is done by comparing and making the percentage of achievement, goals and conditions compared to ideal condition. Based on the evaluation of the implementation of the OHS target in 2016 in PRSG, it was found that all target of K3 in 2016 has been mostly accomplished according to the purpose of OHS to protect the employee, facility, society and environment from potential hazard. (author)