Study of the local neutronic behavior of some CANDU fuel bundles
Creators
- 1. Institute for Nuclear Research, INR, PO Box 78, 1 Campului Street, RO-115400 Mioveni, Arges (Romania)
Description
The objective of this paper is to highlight the local neutronic behavior for three kinds of CANDU fuel bundles. That means to perform a detailed neutronic supercell parameter calculation (of k-eff, detailed flux distributions and end-flux-peaking factors) and then to make a comparative analysis of the obtained results. The considered CANDU fuel bundles are NU37 (Natural Uranium with 37 elements), SEU43 (Slightly Enriched Uranium with 43 elements and 1.1wt % enrichment) and ACR700 (Advanced CANDU Reactor). All fuels are fresh and at nominal power accounted. In order to achieve the proposed objective, a methodology based on WIMS and PIJXYZ codes is used. The both codes are transport codes, consistent and allow a good geometrical representation of the CANDU bundle. The results show differences in the neutronic behavior of the above fuel bundles mainly derived from their enrichment and geometry. (authors)
Availability note (English)
Available from author(s) or National R and D Institute for Cryogenics and Isotopic Technologies - ICIT, PO Box 10, Uzinei Street No. 4, RO-240050 Rm. Valcea (RO)Additional details
Publishing Information
- Publisher
- National R and D Institute for Cryogenics and Isotopic Technologies - ICIT
- Imprint Place
- Rm. Valcea (Romania)
- Imprint Title
- The 12th International ICIT Conference Progress in Cryogenics and Isotopes Separation. Proceedings
- Imprint Pagination
- 273 p.
- Journal Page Range
- p. 115-118
Conference
- Title
- 12. international ICIT conference Progress in Cryogenics and Isotopes Separation. Proceedings
- Dates
- 25-27 Oct 2006
- Place
- Caciulata (Romania)
INIS
- Country of Publication
- Romania
- Country of Input or Organization
- Romania
- INIS RN
- 38015351
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- CANDU TYPE REACTORS; FUEL ELEMENT CLUSTERS; MULTIPLICATION FACTORS; P CODES; REACTOR LATTICES; SLIGHTLY ENRICHED URANIUM; TRANSPORT THEORY; URANIUM; W CODES
- Descriptors DEC
- ACTINIDES; COMPUTER CODES; DIMENSIONLESS NUMBERS; ELEMENTS; ENRICHED URANIUM; FUEL ASSEMBLIES; HEAVY WATER MODERATED REACTORS; ISOTOPE ENRICHED MATERIALS; MATERIALS; METALS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTORS; THERMAL REACTORS; URANIUM
Optional Information
- Notes
- 3 refs., 7 figs., 2 tabs.