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Yupari, Ricardo; Perry, R.T.; Parish, T.A.
10. biennial U.S. TRIGA users' conference. Papers and abstracts1986
10. biennial U.S. TRIGA users' conference. Papers and abstracts1986
AbstractAbstract
[en] This paper is concerned with the computation of 3-D energy dependent neutron fluxes for the NSC reactor using a production code released by the Radiation Shielding Information Centre (RSIC). This code, BOLDVENTURE 2, is a computational system for nuclear reactor analysis. The neutronics module of the system, VENTURE, solves the multigroup neutron diffusion equation by applying the finite difference technique in 1, 2, or 3-D geometry. The NSC reactor was modelled in rectangular coordinates, and seven Energy groups were used to compute the multigroup neutron flux distributions. The seven group cross sections were the same as those used in EXTERMINATOR and they were obtained from GA
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TRIGA Reactors, GA Technologies Inc., San Diego, CA (United States); Texas A and M University, College Station, TX (United States); 380 p; 1986; p. 4.33-4.57; 10. biennial U.S. TRIGA users' conference; College Station, TX (United States); 6-9 Apr 1986; Country of input: International Atomic Energy Agency (IAEA); 3 refs, 13 figs, 1 tab
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Report
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Conference
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DIFFERENTIAL EQUATIONS, DIFFUSION EQUATIONS, ENRICHED URANIUM REACTORS, EQUATIONS, HOMOGENEOUS REACTORS, HYDRIDE MODERATED REACTORS, MATHEMATICS, PARTIAL DIFFERENTIAL EQUATIONS, RADIATION FLUX, REACTORS, RESEARCH AND TEST REACTORS, SOLID HOMOGENEOUS REACTORS, WATER COOLED REACTORS, WATER MODERATED REACTORS
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