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AbstractAbstract
[en] TEMPUL is one dimensional computer code for calculating radial fuel temperature distribution in a fuel immediately after the pulse. Implementation of TEMPUL code was performed to calculate of radial temperature distribution on TRIGA fuel element. The gap between fuel element and cladding is treated to be in contact (without gap), gap is filled with air and gap is filled with helium gas, respectively. Equilateral triangular arrangement coolant channel is assumed. The calculated results on calculation of radial temperature distribution in TRIGA fuel element immediately after the pulse occur relatively high ascending tendency in zirconium rod (radius 0.3175 cm) and fuel element-cladding interface (radius 1.82245 cm) at the first second after pulse with no gap and gap filled with helium gas treatment. Rising of cladding and interface between cladding and coolant average temperature reach up to 500 oC drastically occur in the first second after the pulse. (author)
Original Title
Implementasi Program Tempul untuk Perhitungan Distribusi Suhu Radial pada Elemen Bakar Reaktor Triga setelah Pulsa
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Sukarsono, R.; Ganang Suradjijo (National Nuclear Energy Agency, Yogyakarta (Indonesia)) (eds.); Centre for Research and Development of Advanced Technology, National Nuclear Energy Agency, Yogyakarta (Indonesia); 265 p; ISSN 0216-3128;
; 2002; p. 211-218; Scientific Meeting and Presentation on Basic Research in Nuclear Science and Technology; Pertemuan dan Presentasi Ilmiah Penelitian Dasar Ilmu Pengetahuan dan Teknologi Nuklir; Yogyakarta (Indonesia); 27 Jun 2002; Also available from Center for Development of Nuclear Informatics, National Nuclear Energy Agency, Puspiptek Area, Fax. 62-21-7560923, PO BOX 4274, Jakarta (ID); 6 refs.; 1 tab.; 7 figs.

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