The lesson learned from the severe accident of Fukushima Daiichi nuclear power plant shows that residual heat generated spent fuel should be cooled properly. In order to absorb when station blackout occurs, wickless-heat pipe is proposed used as an alternative passive cooling system in pool. objective this research simulation effect initial pressure and evaporator filling ratio factors influence thermal performance pipe. results will validated with experiment results. model was built...

The research related to thermal management has been significantly inreased, especially for NPP safety. use of passive cooling systems both during the accident and operation become reliable in advanced reactor safety systems. Therefore it should be enhanced through experimental studies investigate heat transfer phenomenon decay transient condition . An i nvestigation performed experimen t using an NC-Queen apparatus constructed with rectangular loop. Piping were consisting tubes SS316L...

The natural circulation is considered in the design of emergency passive core cooling system a nuclear power plant. In that context, order to investigate characteristics circulation, FASSIP-02 experimental loop designed. This paper simulates various operational conditions with different condition heater power, pipe insulation and expansion tank's valve using RELAP5 code. objective obtain best once it built. simulation results show until 50,000 s steady state could not be achieved yet when...

Abstract Reliability and safety are very critical in complex engineering systems such as chemical nuclear industries. Fault tree analysis (FTA) has been widely applied to evaluate the reliability of systems. This approach assumes that always have exact component failure probabilities. However, this assumption is not true real‐world applications. To deal with this, a number scholars integrated fuzzy into FTA whose probabilities cannot be collected. Furthermore, simple arithmetic operations on...

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...

ABSTRAK Analisis Konveksi Alam Teras Reaktor Triga Berbahan Bakar Tipe Pelat MENGGUNAKAN COOLOD-N2. Rencana penghentian produksi elemen bakar jenis TRIGA oleh produsen reaktor TRIGA, sudah seharusnya diantisipasi badan pengoperasi untuk menggantikan tipe silinder tersebut dengan pelat yang tersedia di pasaran. Pada penelitian ini dilakukan perhitungan model teras spesifikasi utama menggunakan bahan U3Si2Al pengayaan uranium sebesar 19,75% dan tingkat muat 2,96 gU/cm3. program COOLOD-N2...

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...

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....

Generation II Nuclear Power Plants (NPPs) have a design weakness as shown by the Fukushima accident. Therefore, III+ NPPs are developed with focus on improvements of fuel technology and thermal efficiency, standardized design, use passive safety system. One type NPP is AP1000 that pressurized water reactor (PWR) has received final acceptance from US-NRC already under construction at several sites in China 2015. The aim this study to investigate behavior performance system verify margin...

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,...

TRIGA 2000 reactor in Bandung is planned to have the fuel element replaced, from cylindrical uranium and zirconium-hydride (U-ZrH) alloy U3Si2-Al plate type of low enriched 19.75% with density 2.96 gU/cm3, while power maintained at 2 MW. This change anticipate discontinuity production. The selection this plate-type supported by fact that such has been produced Indonesia used MPR-30 safely since 2000. core configuration plate-type-fuelled requires coolant flow rate through each channel order...

ABSTRACT THE THERMAL-HYDRAULICS ANALYSIS ON RADIAL AND AXIAL POWER FLUCTUATION FOR AP1000 REACTOR. The reduction of fissile material during reactor operation affects reactivity reduction. Therefore, in order to keep the operating at fixed power, it must be compensated by slowly withdrawing control-rod up. However, will change shape horizontal/axial power distribution and safety margin as well. research carries out calculations core thermal-hydraulics determine effect fluctuations on...

The Fukushima accident resulted in the melting of reactor core due to loss supply coolant when stopped from operating conditions. earthquake and tsunami caused electricity flooding that occurred reactor. absence after shutdown heat accumulation, causing temperature fuel rise beyond its point. In early stages accident, operator could not determine severity percentage damaged. available data was based on radiation exposure environment reported by authorities. aim this paper is conditions doses...

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...

Abstract Innovative Research Reactor 50 MW (RRI-50) is a conceptual design of an Indonesia's high-power innovative research reactor, which designed to produce maximum neutron flux as high 1.0 × 10 15 n/cm 2 s and thermal 5.0 14 s. In this study, the basis accident slow reactivity insertion carried out. Reactivity (RIA) caused by inadvertent withdrawal all fuel rod at normal rate simulated using PARET-ANL transient code. simulation assumed occur when reactor in operation power low level....

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,...

Environmental radiation monitoring is one of the important efforts in protecting society and environment from hazards, both natural artificial. The presence three nuclear research reactors plans to build a power plant reactor prompted Indonesia prepare system for safety security (SPRKK). goal study provide an appropriate method developing support development near future. For this preliminary study, author developed code program using Gaussian distribution model approach predicting...