Study of Fuel Rods Axial Enrichment Distribution Effect on the Neutronic Parameters of the Reactor Core
Creators
- 1. Islamic Azad University, Science and Research, Nuclear Engineering Department, Tehran (Iran, Islamic Republic of)
Description
Optimization of the fuel burn up is an important issue in nuclear reactor fuel management and technology. Radial enrichment distribution in the reactor core is a conventional method and axial enrichment is constant along the fuel rod. In this article, the effects of axial enrichment distribution variation on neutronic parameters of PWR core are studied. The axial length of the core is divided into ten sections, considering axial enrichment variation and leaving the existing radial enrichment distribution intact. This study shows that the radial and axial power peaking factors are decreased as compared with the typical conventional core. In addition, the first core lifetime lasts 30 days longer than normal PWR core. Moreover, at the same time boric acid density is 0.2 g/kg at the beginning of the cycle. The flux shape is also flat at the beginning of the cycle for the proposed configuration of the axially enrichment distribution.
Availability note (English)
Available from Atomic Energy Organization of IranAdditional details
Additional titles
- Original title (Persian)
- Barresi-e asar-e tozi'e mehvari-e ghena-ye mile-haye sookht bar parametr-haye notroni-e ghalb-e reaktor-haye hastei-e ghodrat
Publishing Information
- Journal Title
- Journal of Nuclear Science and Technology
- Journal Issue
- no.59
- Journal Page Range
- p. 15-21
- ISSN
- 1735-1871
INIS
- Country of Publication
- Iran, Islamic Republic of
- Country of Input or Organization
- Iran, Islamic Republic of
- INIS RN
- 43105842
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- ENRICHMENT; FUEL MANAGEMENT; FUEL RODS; NEUTRON FLUX; PEAK LOAD; PWR TYPE REACTORS; REACTOR CORES; SPATIAL DISTRIBUTION
- Descriptors DEC
- DISTRIBUTION; ENRICHED URANIUM REACTORS; FUEL ELEMENTS; MANAGEMENT; NUCLEAR MATERIALS MANAGEMENT; POWER REACTORS; RADIATION FLUX; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS