Determination of the neutron flux in the reactor zones with the strong neutron absorption and leakage
Creators
- 1. Milosevic, M.
- 2. Center for Nuclear Technologies and Research, Vinca Institute of Nuclear Sciences, P.O.Box 522, 11001 Belgrade (Serbia)
Description
The procedures for the numerical and experimental determination of the neutron flux in the zones with the strong neutron absorption and leakage are described in this paper. The proposed procedures have been applied for the determination of the neutron flux in the internal neutron converter used with the RB reactor core configuration number 114. This paper shows: a) that the full heterogeneous core of complicate geometry, as the RB reactor core configuration No. 114, can be reliably calculated using the equivalence approach implemented in the VEGA2DAN code as a complement to the KENO-V.a multigroup Monte Carlo code; and b) a possibility of the RB reactor core configuration No. 114 for the irradiation of large samples in the field of fast neutrons.
Files
41123695.pdf
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Additional details
Publishing Information
- Publisher
- Institute of Nuclear Sciences VINCA
- Imprint Place
- Belgrade (Serbia)
- ISBN
- 86-7306-076-1
- Imprint Title
- Proceedings of the 5th Yugoslav Nuclear Society Conference (YUNSC-2004)
- Imprint Pagination
- 544 p.
- Journal Page Range
- p. 207-215
- Report number
- INIS-CS--0005
Conference
- Title
- 5. International Yugoslav Nuclear Society Conference
- Acronym
- YUNSC-2004
- Dates
- 27-30 Sep 2004
- Place
- Belgrade (Yugoslavia)
INIS
- Country of Publication
- Serbia
- Country of Input or Organization
- Serbia
- INIS RN
- 41123695
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S73: NUCLEAR PHYSICS AND RADIATION PHYSICS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- COMPUTER CALCULATIONS; CONFIGURATION CONTROL; DOSE RATES; ENERGY SPECTRA; EVALUATED DATA; EXPERIMENTAL DATA; IRRADIATION; K CODES; MONTE CARLO METHOD; NEUTRON CONVERTERS; NEUTRON FLUX; NEUTRON LEAKAGE; RADIATION DOSES; R-B REACTOR; REACTOR CORES; SAFETY ANALYSIS; V CODES
- Descriptors DEC
- CALCULATION METHODS; COMPUTER CODES; CONTROL; DATA; DOSES; EXPERIMENTAL REACTORS; HEAVY WATER MODERATED REACTORS; INFORMATION; NATURAL URANIUM REACTORS; NUMERICAL DATA; RADIATION FLUX; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; SPECTRA; TRAINING REACTORS; ZERO POWER REACTORS
Optional Information
- Notes
- 4 figs., 3 tabs.; This record replaces 36115467