Analysis of natural convection in TRIGA reactor core plate types fueled using COOLOD-N2
- 1. Pusat Sains dan Teknologi Nuklir Terapan – BATAN, Bandung (Indonesia)
- 2. Pusat Teknologi Reaktor dan Keselamatan Nuklir – BATAN, Serpong (Indonesia)
Description
Any pretensions to stop the production of TRIGA fuel elements by TRIGA reactor fuel elements manufacturer should be anticipated by the operating agency of TRIGA reactor to replace the cylinder type fuel element with plate type fuel element that available on the market. In this study, the calculation of U3Si2Al fuel with uranium enrichment of 19.75 % and a load level of 2.96 gU/cm3 was performed. Analyses were performed using the validated COOLOD - N2 program. TRIGA conversion core configurations of fuel plate type are composed of 16 fuel elements, 4 control elements and 1 irradiation facilities which are located in the middle of core. The calculation results showed that if the cooling temperature was 37°C, and the ratio of radial power peaking factor ≤ 1.92, then the maximum power that can be operated on free convection mode of operation was 600 kW. The thermalhydraulic characteristic obtained such as coolant temperature at the outlet side, cladding and meat were 82.39°C, 108.88°C and 109.02°C respectively, while the ΔTONB (Temperature Onset of Nucleate Boiling) was 7.18°C and OFIR (Onset of flow instability ratio) value was 1.03. The results are expected to be used as a reference for determining the power level of the TRIGA reactor core plate types fueled. (author)
Additional details
Additional titles
- Original title (Indonesian)
- Analisis konveksi alam teras reaktor TRIGA berbahan bakar tipe pelat menggunakan COOLOD-N2
Publishing Information
- Journal Title
- Jurnal Teknologi Reaktor Nuklir
- Journal Volume
- 17
- Journal Issue
- 2
- Journal Page Range
- p. 67-78
- ISSN
- 1411-240X
INIS
- Country of Publication
- Indonesia
- Country of Input or Organization
- Indonesia
- INIS RN
- 48056869
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- COMPUTERIZED SIMULATION; FUEL PLATES; NATURAL CONVECTION; PROGRAMMING; REACTOR CORES; TRIGA TYPE REACTORS
- Descriptors DEC
- CONVECTION; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FUEL ELEMENTS; HEAT TRANSFER; HOMOGENEOUS REACTORS; HYDRIDE MODERATED REACTORS; MASS TRANSFER; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; SIMULATION; SOLID HOMOGENEOUS REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 17 refs., 2 tabs., 10 figs.