Neutron flux evaluation in the lattice cell of the CANDU-600 reactor
Creators
- 1. Center for Nuclear Objectives Engineering, R-76900 Bucharest, P.O.Box MG-4, (Romania)
Description
The neutron flux evaluation for a CANDU reactor cell is presented. A unit cell consisting of a single fuel channel and the appropriate amount of moderator (D2 O) is considered. The geometrical model is composed of 10 regions: 6 regions with the same fuel elements, sheaths and D2 O coolant, which differ only by geometry and 4 regions formed by pressure tube, CO2, calandria tube and moderator. The microscopic cross sections were selected from DLC-2 library for P0 order of scattering using the program RETOG. The macroscopic cross sections for homogenized regions were calculated with TAPEMA code. The neutron fluxes have been computed by ANISN in the S4 approximation and cylindrical geometry. The results are plotted for fast energy groups (> 10 MeV) as a function of the cell radius. (Author)
Availability note (English)
Available from Romanian Physical Society, R-76900 Bucharest-Magurele, P.O.Box MG-6, (RO).Additional details
Publishing Information
- Publisher
- Institute of Atomic Physics. Information and Documentation Office.
- Imprint Place
- Bucharest-Magurele (Romania)
- Imprint Title
- National Physics Conference. Iasi, September 21-24, 1992. Paper Abstracts
- Imprint Pagination
- 150 p.
- Journal Page Range
- p. 118.
Conference
- Title
- National Physics Conference.
- Dates
- 21-24 Sep 1992.
- Place
- Iasi (Romania).
INIS
- Country of Publication
- Romania
- Country of Input or Organization
- Romania
- INIS RN
- 26008557
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- A CODES; CERNAVODA-1 REACTOR; CYLINDRICAL CONFIGURATION; FUEL CHANNELS; GEOMETRY; MEV RANGE 10-100; NEUTRON FLUX; R CODES; REACTOR CELLS; REACTOR LATTICES; T CODES
- Descriptors DEC
- CANDU TYPE REACTORS; COMPUTER CODES; CONFIGURATION; ENERGY RANGE; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; MATHEMATICS; MEV RANGE; NATURAL URANIUM REACTORS; PHWR TYPE REACTORS; POWER REACTORS; PRESSURE TUBE REACTORS; RADIATION FLUX; REACTOR CHANNELS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS