Effect of Utilization of Silicide Fuel with the Density 4.8 gU/cc on the Kinetic Parameters of RSG-GAS Reactor
Creators
- 1. Centre for Reactor Technology and Nuclear Safety, National Nuclear Energy Agency, Serpong (Indonesia)
Description
Presently, the RSG-GAS reactor using silicide fuel element of 2.96 gU/cc. For increasing reactor operation time, its planning to change to higher density fuel. The kinetic calculation of silicide core with density 4.8 gU/cc has been carried out, since it has an influence on the reactor operation safety. The calculated kinetic parameters are the effective delayed neutron fraction, the delayed neutron decay constant, prompt neutron lifetime and feedback reactivity coefficient very important for reactor operation safety. the calculation is performed in 2-dimensional neutron diffusion-perturbation method using modified Batan-2DIFF code. The calculation showed that the effective delayed neutron fraction is 7. 03256x10-03, total delay neutron time constant is 7.85820x10-02 s-1 and the prompt neutron lifetime is 55.4900 μs. The result of prompt neutron lifetime smaller 10 % compare with silicide fuel of 4.8 gU/cc. The calculated results showed that all of the feedback reactivity coefficient silicide core 4.8 gU/cc is negative. Totally, the feedback reactivity coefficient of silicide fuel of 4.8 gU/cc is 10% less than that of silicide fuel of 2.96 gU/cc. The results shown that kinetic parameters result decrease compared with the silicide core with density 2.96 gU/cc, but no significant influence in the RSG-GAS reactor operation. (author)
Files
45095687.pdf
Files
(3.7 MB)
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Additional details
Additional titles
- Original title (Indonesian)
- Efek Penggunaan Elemen Bakar Sillsida Kerapatan 4.8 gU/cc terhadap Sifat Kinetika Reaktor RSG-GAS
Publishing Information
- Publisher
- National Nuclear Energy Agency
- Imprint Place
- Yogyakarta (Indonesia)
- Imprint Title
- Proceedings of the Scientific Meeting and Presentation on Basic Research in Nuclear of the Science and Technology part I : Physics and Nuclear Reactor
- Imprint Pagination
- 427 p.
- Journal Page Range
- p. 82-89
- ISSN
- 0216-3128
- Report number
- INIS-ID--059
Conference
- Title
- Scientific Meeting and Presentation on Basic Research in Nuclear Science and Technology
- Original Conference Title
- Pertemuan dan Presentasi Ilmiah Penelitian Dasar Ilmu Pengetahuan dan Teknologi Nuklir
- Dates
- 10 Jul 2007
- Place
- Yogyakarta (Indonesia)
INIS
- Country of Publication
- Indonesia
- Country of Input or Organization
- Indonesia
- INIS RN
- 45095687
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ADJOINT FLUX; DELAYED NEUTRON FRACTION; DENSITY; FUEL CELLS; FUEL ELEMENTS; GA SIWABESSY REACTOR; NEUTRON DIFFUSION EQUATION; NEUTRON FLUX; PLUTONIUM; PROGRAMMING; REACTOR KINETICS; REACTOR OPERATION; REACTOR SAFETY; SILICIDES; URANIUM
- Descriptors DEC
- ACTINIDES; DIFFERENTIAL EQUATIONS; DIFFUSION EQUATIONS; DIRECT ENERGY CONVERTERS; ELECTROCHEMICAL CELLS; ELEMENTS; ENRICHED URANIUM REACTORS; EQUATIONS; IRRADIATION REACTORS; KINETICS; MATERIALS TESTING REACTORS; METALS; NEUTRON FLUX; OPERATION; PARTIAL DIFFERENTIAL EQUATIONS; PHYSICAL PROPERTIES; POOL TYPE REACTORS; RADIATION FLUX; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SAFETY; SILICON COMPOUNDS; THERMAL REACTORS; TRANSURANIUM ELEMENTS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 5 refs.; 7 tabs.; 3 figs. Imprint:Prosiding Pertemuan dan Presentasi Ilmiah Penelitian Dasar Ilmu Pengetahuan dan Teknologi Nuklir buku I : Fisika dan Reaktor Nuklir