Using LEU+Th mixed oxide fuel in CANDU reactors
Creators
- 1. Institute for Nuclear Research (ICN), Mioveni-AG (Romania)
- 2. Politehnica University, Bucharest (Romania)
Description
Thorium-based fuel alternatives for PHWR/CANDU were extensively explored in the last decades, given the Thorium economic benefits and CANDU reactors flexibility. Both 37-and 43-element bundles were studied in this paper. The uranium enrichment ranged between 5 and 10 wt% U235, while the Th/U ratio was 1.5 ÷ 2.333. The (LEU+Th)O2 fuel bundles are supposed to be loaded in every channel of the CANDU core, in a homogenous "once-through Thorium" (OTT) core. Transport cells calculations were performed for the (LEU+Th)O2 fuel using the lattice codes DRAGON and WIMS and the associated nuclear data library based on ENDF/B-VII. The mixed oxide fuel is meant to replace the CANDU one, therefore key features were investigated to assess its economic performances: maximum burnup, power peaking factors, relative fissile yield and utilisation. The results are encouraging, due to this fuel potential to reach higher fuel burnup. (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 1/3
- Imprint Pagination
- 344 p.
- Journal Page Range
- p. 55-62
- ISSN
- 2066-2955
- Report number
- INIS-RO--0012
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
- 49086191
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BURNUP; CANDU TYPE REACTORS; FLEXIBILITY; FUEL ELEMENT CLUSTERS; ISOTOPE SEPARATION; MIXED OXIDE FUELS; NUCLEAR DATA COLLECTIONS; OXIDES; PERFORMANCE; PHWR TYPE REACTORS; POTENTIALS; THORIUM; TRANSPORT; URANIUM; URANIUM 235; YIELDS
- Descriptors DEC
- ACTINIDE NUCLEI; ACTINIDES; ALPHA DECAY RADIOISOTOPES; CHALCOGENIDES; ELEMENTS; ENERGY SOURCES; EVEN-ODD NUCLEI; FUEL ASSEMBLIES; FUELS; HEAVY NUCLEI; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; INTERNAL CONVERSION RADIOISOTOPES; ISOMERIC TRANSITION ISOTOPES; ISOTOPES; MATERIALS; MECHANICAL PROPERTIES; METALS; MINUTES LIVING RADIOISOTOPES; NUCLEAR FUELS; NUCLEI; OXYGEN COMPOUNDS; POWER REACTORS; PRESSURE TUBE REACTORS; RADIOISOTOPES; REACTOR MATERIALS; REACTORS; SEPARATION PROCESSES; SOLID FUELS; SPONTANEOUS FISSION RADIOISOTOPES; TENSILE PROPERTIES; THERMAL REACTORS; URANIUM ISOTOPES; YEARS LIVING RADIOISOTOPES
Optional Information
- Notes
- 11 refs.