Analysis of flow distribution for high density fuel research reactor design
- 1. Center for Reactor Technology and Nuclear Safety, National Nuclear Energy Agency, Kawasan Puspiptek Gd 80, Serpong, Tangerang Selatan 15314 (Indonesia)
Description
An analysis to determine the flow rate distribution and heat balance on the new high density fuel research reactor designed has been carried out using Caudvap and Coolod-N codes. The analysis method are deciding three core models to be analyzed, determining the flow rate distribution and pressure drop across the core as a function of core flow rate from 500 kg/s to 1300 kg/s. On the limitation pressure drop across the core oft 0.5 bar, it was found that the total core flow rate of A, B and C models, were 482.56 kg/s, 415.11 kg/s and 472.41 kg/s, respectively. The calculation of coolant velocity in the fuel element as a function of core flow rate from 500 kg/s to 1300 kg/s using the Caudvap code gave results 3.71 m/s to 9.58 m/s, whereas using the Coolod-N code obtained 3.74 m/s to 9.70 m/s, the deviation ranges of the two calculations were 0.88 % to 1.19 %. Based on the heat balance as a reference, that minimum enthalpy required for RSG-GAS was 50 kJ/kg, so it was found that the A, B and C models required a minimum core flow rate of 780 kg/s, 852 kg/s and 801 kg/s, respectively, engaged with the pressure drop across the core of 1.25 bar, 1.74 bar and 1.54 bar, respectively, whereas the coolant velocity in the fuel elements of 5.68 m/s, 6.73 m/s and 6.33 m/s, respectively. In terms of the cooling aspects of the fuel element, it was concluded that the A and C models better than B model. (author)
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Additional details
Additional titles
- Original title (Indonesian)
- Analisis distribusi laju alir desain teras reaktor riset berbahan bakar tingkat muat tinggi
Publishing Information
- Publisher
- Center for Reactor Technology and Nuclear Safety, National Nuclear Energy Agency
- Imprint Place
- Tangerang Selatan (Indonesia)
- Imprint Title
- Proceedings of the 18"t"h National Seminar on Technology and Safety for Nuclear Power Plants and Nuclear Facilities
- Imprint Pagination
- 422 p.
- Journal Page Range
- p. 97-108
- ISSN
- 0854-2910
- Report number
- INIS-ID--114
Conference
- Title
- 18. National Seminar on Technology and Safety of Nuclear Power Plants and Nuclear Facilities
- Original Conference Title
- Seminar Nasional ke-18 Teknologi dan Keselamatan PLTN Serta Fasilitas Nuklir
- Dates
- 29 Sep 2012
- Place
- Bandung (Indonesia)
INIS
- Country of Publication
- Indonesia
- Country of Input or Organization
- Indonesia
- INIS RN
- 54113124
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTER CODES; FLOW RATE; FUEL ELEMENTS; GA SIWABESSY REACTOR; HIGH-TEMPERATURE FUEL CELLS; PRESSURE DROP; REACTOR CORES; RESEARCH REACTORS
- Descriptors DEC
- DIRECT ENERGY CONVERTERS; ELECTROCHEMICAL CELLS; ENRICHED URANIUM REACTORS; FUEL CELLS; IRRADIATION REACTORS; MATERIALS TESTING REACTORS; POOL TYPE REACTORS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 12 refs.; 4 tabs.; 8 figs. Imprint:Prosiding Seminar Nasional ke-18 Teknologi dan Keselamatan PLTN Serta Fasilitas Nuklir