The decay heat that is produced by nuclear reactor spent fuel must be cooled in a storage pool. A wickless pipe or vertical two-phase closed thermosyphon (TPCT) used to remove this heat. objective of research investigate the thermal performance prototype model for large-scale TPCT as passive cooling system An experimental investigation and numerical simulation using RELAP5/MOD 3.2 were performance. effects initial pressure, filling ratio, load analyzed. Demineralized water was working fluid....

In the future, use of passive cooling system without electrical power input become highly considered to be implemented in design nuclear reactor safety system. Moreover, lessons learned from Fukushima-Daiichi accident encourage incorporation such The is aimed cope with both bases as well severe accidents. natural circulation one example parameter features being widely considered. However, some parameters involving are still investigated, particular problem flow instability. BATAN designing a...

As in many other energy generating system, the nuclear power plant, use of natural circulation principle for safety system is increasingly considered. The could play an important role providing emergency cooling reactor. reliability plant should be demonstrated order to assure level its safety. FASSIP-02 a large scale test facility study plant. To characteristics and help validating design FASSIP-02, numerical using RELAP5 code undertaken. Based on existing simulation done with two...

The performance test of the self-power neutron detector (SPND) and its utilization for flux mapping Kartini reactor core have been done. In this test, measured current from SPND output was calibrated by using 197Au foil activation method. activated covered cadmium fast detection bare total detection. Therefore, can be done thermal, fast, distributions at core. result showed that sensitivity with 103Rh emitter is still good in performance, i.e. 3.70 x 10−21 A/nv-cm. performing well compared...

The heat pipe is a device that can transfer very effectively and passively. Heat pipes are widely used as thermal management tools in various fields, including nuclear reactors. Although have geometries shapes, consist of three parts: the evaporator, adiabatic, condenser. adiabatic will pass working fluid gas from evaporator to condenser liquid evaporator. There limited studies on effect length performance. Therefore, research has been carried out for fixed was conducted by numerical...

The loop heat pipe (LHP) has the potential to be used as a passive cooling system in small modular reactors. research objective is study thermal dynamics of LHP with capillary tube wick using non-linear autoregressive exogenous (NARX) based on neural network. network identification was carried out MATLAB platform. experiment data obtained identify wick. temperature water an evaporator source varied at 60, 70, 80, and 90 °C. charged demineralized filling ratio 100 %. air coolant condenser...

Abstract Kartini reactor in Yogyakarta is a nuclear with low thermal power of 100 kW that mainly used for education, training, and research. For purpose, measuring neutron flux controlling the are important operational parameters. The Fission Chamber (FC) type detector main component operation safety system measures outer core. As FC placed fixed location, numerical calculation model needed to know all core regions. In this study, MCNPX code used. first step validate experimental...

Heat pipe is considered being used as a passive system to remove residual heat that generated from reactor core when incident occur or spent fuel pool. The present research aimed studying the characteristics of straight removal system. As an initial step, numerical simulation was conducted simulate best experimental design set up prepared for next step research. objective get thermal hydraulic characteristic due variation flux source. RELAP5 MOD 3.2 code and analyze characteristics....

Natural circulation has an important role in the safety system of a nuclear reactor. It is part passive system, which operated without any external prime mover. The behavior natural shall be known to effectively incorporated This paper describes preliminary results study on conducted at vertical rectangular experimental facility FASSIP-01. RELAP5 code used simulate experiment. goal validity RELAP 5 model analyze simulation could provide reasonable good describing established loop However,...

Organizations should increase safety to minimize the harmful effects of nuclear materials. Additionally, organizations take measures protect security culture within organization itself. This paper covers National Nuclear Energy Agency Indonesia's (BATAN's) promotion and self- assessment projects, which is based on International Atomic Agency's (IAEA) methodology.

One of the most important aspects nuclear safety systems is reactor cooling system, both in under normal conditions and accident conditions. Severe occurrences due to failure active led growing importance role passive be implemented current future systems, particular. Passive system experiments conducted understand determine what parameters affect natural circulation flow rate, especially local phenomena that occur. So purpose this study was investigate effects temperature changes on cold...

When an anomaly is discovered during a thermal inspection of industrial equipment, the diagnosis finding heat source made more difficult by presence insulation. The use Conjugate Gradient Method (CGM) to solve unknown flux in Inverse Heat Conduction Problem (IHCP) under insulation condition has been discussed. This method used predict utilizing temperature data at any points measurement. study deals with structure 2D thin plate steady state. A copper thickness 1 mm as specimen. White glass...

A postulated loss of coolant accident (LOCA) shall be analyzed to assure the safety a research reactor. The analysis such could performed using best estimate thermal-hydraulic codes, as RELAP5. This study focuses on LOCA in TRIGA-2000 due pipe and beam tube break. objective is understand effect break size actuating time emergency core cooling system (ECCS) consequences assess RELAP/SCDAPSIM codes. Three different were studied. results confirmed that larger size, faster blow down. But, siphon...

To improve the thermal safety of a nuclear power plant, wickless-heat pipe is proposed as passive cooling system on an emergency tank. Heat will keep water in tank normal operating temperature. The objective this preliminary research to investigate characteristics pipe. RELAP/SCDAPSIM/MOD3.4 thermal-hydraulic code was used analyze simulation results be basis for designing future experimental investigations influence hot temperature and mass flow rate coolant jacket were investigated. varied,...

To enhance the thermal safety in case of station blackout, a wickless-heat pipe is proposed as an alternative passive cooling system technology to remove decay heat generation nuclear spent fuel storage pool. The objectives this research are investigate transfer phenomena vertical straight using Graphene nanofluid working fluid and study effect on performance. investigation was conducted 6 meters height 0.1016 m inside diameter pipe. In research, with 1 % weight concentration used fluid....

Identifying and mitigating insider threats through a trustworthiness program in nuclear facilities is great challenge. Therefore, it important to develop tool for assessing behavior during the life cycle of employees. National Nuclear Energy Agency (BATAN) Indonesia conducted that includes supervisor review, medical appraisal, management decision, trust official review. All current methods need an expert's opinion analyzing information determining level threat due insider. The method...

The Kartini research reactor core cooling uses natural convection. Primary system is used to cool coolant by circulating in tank a heat exchanger dissipating the secondary and back tank. injected through diffuser located above order dilute N-16 radionuclide. However, it turns out that primary flow affected circulation core. This study was conducted effect of on at various power, as well determine characteristics experimental focused hot channel (ring B). operated with power 50 kW, 75 100 kW....