Evaluation of transient loss of coolant accident in Kartini research reactor at 100 kW power
Creators
- 1. Pusat Pengkajian Sistem dan Teknologi Pengawasan Instalasi dan Bahan Nuklir, Badan Pengawas Tenaga Nuklir, Jl. Gajah Mada No. 8 Jakarta Pusat (Indonesia)
Description
Safety analysis method on research reactor in Indonesia needs to be developed. Calculation using analytical method needs to be added with computer code calculation in order to make calculation faster and accurate. BAPETEN is the regulatory body which has an authority to evaluate and publish a license of nuclear reactor. BAPETEN needs a lot of human resources that understand and able to use various computer codes, among other is RELAP5 MOD3.4 computer code in anticipating nuclear power plant era in the future. From the series of simulation, it is concluded that RELAP/SCDAP/MOD 3.4 is able to be used in safety assessment of safety analysis report of Kartini 100 kW research reactor and able to simulate loss of coolant accident that postulated in Kartini research reactor safety analysis report. (author)
Files
54113091.pdf
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(668.2 kB)
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Additional details
Additional titles
- Original title (Indonesian)
- Evaluasi kejadian transien susut air pendingin reaktor riset TRIGA Kartini pada daya 100 kW
Publishing Information
- Publisher
- Center for Reactor Technology and Nuclear Safety, National Nuclear Energy Agency
- Imprint Place
- Tangerang Selatan (Indonesia)
- Imprint Title
- Proceedings of the 17"t"h National Seminar on Technology and Safety for Nuclear Power Plants and Nuclear Facilities
- Imprint Pagination
- 724 p.
- Journal Page Range
- p. 427-435
- ISSN
- 0854-2910
- Report number
- INIS-ID--113
Conference
- Title
- 17. National Seminar on Technology and Safety of Nuclear Power Plants and Nuclear Facilities
- Original Conference Title
- Seminar Nasional ke-17 Teknologi dan Keselamatan PLTN Serta Fasilitas Nuklir
- Dates
- 1 Oct 2011
- Place
- Yogyakarta (Indonesia)
INIS
- Country of Publication
- Indonesia
- Country of Input or Organization
- Indonesia
- INIS RN
- 54113091
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACCIDENTS; COMPUTER CALCULATIONS; COMPUTER CODES; INDONESIA; KARTINI-PPNY REACTOR; LICENSES; LOSS OF COOLANT; NUCLEAR POWER PLANTS; REACTORS; RESEARCH REACTORS; SAFETY ANALYSIS; SIMULATION; TRANSIENTS
- Descriptors DEC
- ACCIDENTS; ASIA; DEVELOPING COUNTRIES; ENRICHED URANIUM REACTORS; HOMOGENEOUS REACTORS; HYDRIDE MODERATED REACTORS; ISLANDS; NUCLEAR FACILITIES; POWER PLANTS; REACTOR ACCIDENTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SOLID HOMOGENEOUS REACTORS; THERMAL POWER PLANTS; TRIGA TYPE REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 5 refs.; 10 figs. Imprint:Prosiding Seminar Nasional ke-17 Teknologi dan Keselamatan PLTN Serta Fasilitas Nuklir