Safety analysis of RSG-GAS Silicide core using one line cooling system
Description
In the frame of minimizing the operation-cost, operation mode using one line cooling system is being evaluated. Maximum reactor has been determined and to continuing this program, steady state and transient analysis were done. The analysis was done by means of a core thermal hydraulic code, COOLOD-N, and PARET. The codes solves core thermal hydraulic equation at steady state conditions and transient, respectively. By using silicide core data and coast down flow rate as the input, thermal hydraulics parameters such as fuel cladding and fuel meat temperatures as well as safety margin against flow instability were calculated. Imposing the safety criteria to the results of steady state and transient analysis, maximum permissible power for this operation was obtained as much as 17.1 MW
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Additional details
Additional titles
- Original title (Indonesian)
- Analisis keselamatan moda satu jalur pendingin teras Silisida RSG-GAS
Publishing Information
- Publisher
- National Nuclear Energy Agency
- Imprint Place
- Serpong (Indonesia)
- Imprint Title
- Proceeding of the Seminar Result of Research Reactor Safety Technology Research Centre
- Imprint Pagination
- 235 p.
- Journal Page Range
- p. 137-145
- ISSN
- 0854-5278
- Report number
- INIS-ID--038
Conference
- Title
- Seminar Result of Research Reactor Safety Technology Research Centre 2002
- Original Conference Title
- Seminar Hasil Penelitian P2TRR tahun 2002
- Dates
- 4-5 Feb 2003
- Place
- Serpong (Indonesia)
INIS
- Country of Publication
- Indonesia
- Country of Input or Organization
- Indonesia
- INIS RN
- 38115347
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- GA SIWABESSY REACTOR; HEAT EXCHANGERS; POWER; PROGRAMMING; REACTOR COOLING SYSTEMS; REACTOR CORES; REACTOR OPERATION; SAFETY ANALYSIS; SILICIDES; STEADY-STATE CONDITIONS; THERMAL HYDRAULICS; TRANSIENTS
- Descriptors DEC
- COOLING SYSTEMS; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; FLUID MECHANICS; HYDRAULICS; IRRADIATION REACTORS; MATERIALS TESTING REACTORS; MECHANICS; OPERATION; POOL TYPE REACTORS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SILICON COMPOUNDS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 9 refs; 2 tabs; 5 figs Imprint:Prosiding Seminar Hasil Penelititan P2TRR Tahun 2002