Assesment of nue fuel element performance in normal operating conditions
- 1. RATEN Institute for Nuclear Research, Pitesti (Romania)
- 2. University of Pitesti (Romania)
Description
Due to its neutron economy, versatility of fuel channel and simplicity of fuel bundle design, CANDU reactors have a unique ability of efficiently using alternative fuel, such as: depleted uranium (DU), recycled uranium (RU), mixed oxide of Thorium and Plutonium ((Pu,Th)MOX) and natural uranium equivalent (NUE). This paper outlines the results on the investigation of two analysed cases (NUE versus 37S) with ELESIM computer code, aimed to evaluate the fuel behaviour in normal operating conditions. ELESIM computer code estimates the nuclear fuel elements performance parameters, for a given history power, using one-dimensional models for heat generation, temperature distribution, fission gas release and pellet to sheath heat transfer. The fuel bundle power distribution respectively for each ring corresponding to a fuel channel was obtained with LEGENTR3D, WIMS and DRAGON programs. (authors)
Additional details
Publishing Information
- Publisher
- Institute for Nuclear Research - Pitesti
- Imprint Place
- Pitesti (Romania)
- Imprint Title
- Proceedings of NUCLEAR 2017 international conference on sustainable development through nuclear research and education. Part 3/3
- Imprint Pagination
- 129 p.
- Journal Page Range
- p. 65-71
- ISSN
- 2066-2955
- Report number
- INIS-RO--0014
Conference
- Title
- 10. annual international conference on sustainable development through nuclear research and education
- Acronym
- NUCLEAR 2017
- Dates
- 24-26 May 2017
- Place
- Pitesti (Romania)
INIS
- Country of Publication
- Romania
- Country of Input or Organization
- Romania
- INIS RN
- 49086235
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ADMINISTRATIVE PROCEDURES; ALTERNATIVE FUELS; CANDU TYPE REACTORS; COMPUTER CODES; COMPUTERS; DEPLETED URANIUM; DESIGN; FISSION; FISSION PRODUCT RELEASE; FISSION PRODUCTS; FUEL CHANNELS; FUEL ELEMENT CLUSTERS; FUEL ELEMENTS; HEAT; HEAT TRANSFER; NATURAL URANIUM; NEUTRON FLUX; NEUTRONS; NUCLEAR FUELS; ONE-DIMENSIONAL CALCULATIONS; OXIDES; PELLETS; PERFORMANCE; PLUTONIUM; POWER DISTRIBUTION; RINGS; SULFUR 37; TEMPERATURE DISTRIBUTION; THORIUM
- Descriptors DEC
- ACTINIDES; BARYONS; BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; CHALCOGENIDES; ELEMENTARY PARTICLES; ELEMENTS; ENERGY; ENERGY SOURCES; ENERGY TRANSFER; EVEN-ODD NUCLEI; FERMIONS; FUEL ASSEMBLIES; FUELS; HADRONS; HEAVY WATER MODERATED REACTORS; ISOTOPES; LIGHT NUCLEI; MATERIALS; METALS; MINUTES LIVING RADIOISOTOPES; NUCLEAR REACTIONS; NUCLEI; NUCLEONS; OXYGEN COMPOUNDS; POWER REACTORS; PRESSURE TUBE REACTORS; RADIATION FLUX; RADIOACTIVE MATERIALS; RADIOISOTOPES; REACTOR CHANNELS; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; SULFUR ISOTOPES; THERMAL REACTORS; TRANSURANIUM ELEMENTS; URANIUM
Optional Information
- Notes
- 6 figs., 3 tabs.