Preliminary Study on Fuel Enrichment Increase for Accident Tolerant Fuel Concept
Creators
- 1. Nuclear Fuel R&D Center, China Nuclear Power Technology Research Institute (CNPRI), China General Nuclear Power Corporation (CGN) (China)
Description
Conclusions: For some ATF candidate materials, increasing 235U enrichment could be an important solution to balance the safety performance and cost. • In order to match the margin in mechanical design, FeCrAl cladding should have almost same thickness with Zircaloy of conventional PWR fuel. In that case the enrichment should be increased by 0.96% to match the cycle length of reactor core. • For a 13×13 fuel rod array configuration, under the limit of 20% enrichment, requirement of UO2 and UN kernel diameters are 730μm and 650μm, when the packing fraction is set to be 45%; while if the diameter is set to be 700μm, packing fraction of UO2 and UN kernel should reach at 50% and 36%. • Taking no account of fuel assembly fabrication and spent fuel disposal, when the enrichment reaches at 20%, total cost of four components (including natural uranium, conversion, enrichment and depleted uranium disposal) increases about 17% compared with 5% enriched fuel. • For the ATF development, general assessment need to be considered from aspects of fuel cost, core design, fuel design, licensing issue, influence on fuel cycle, etc., in order to evaluate the feasibility of increasing fuel enrichment.
Files
51105429.pdf
Files
(2.7 MB)
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Additional details
Identifiers
Publishing Information
- ISBN
- 978-92-0-110920-0
- Imprint Title
- Light Water Reactor Fuel Enrichment beyond the Five Per Cent Limit: Perspectives and Challenges
- Imprint Pagination
- vp.
- Journal Page Range
- 22 p.
- ISSN
- 1011-4289
- Report number
- IAEA-TECDOC--1918(SUPPLEMENTARY FILES)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 51105429
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Descriptors DEI
- ACCIDENT-TOLERANT NUCLEAR FUELS; DEPLETED URANIUM; DESIGN; FUEL ASSEMBLIES; FUEL RODS; NATURAL URANIUM; PWR TYPE REACTORS; REACTOR CORES; SPENT FUELS; URANIUM 235; URANIUM DIOXIDE; ZIRCALOY
- Descriptors DEC
- ACTINIDE COMPOUNDS; ACTINIDE NUCLEI; ACTINIDES; ALLOYS; ALPHA DECAY RADIOISOTOPES; CHALCOGENIDES; ELEMENTS; ENERGY SOURCES; ENRICHED URANIUM REACTORS; EVEN-ODD NUCLEI; FUEL ELEMENTS; FUELS; HEAVY NUCLEI; INTERNAL CONVERSION RADIOISOTOPES; ISOMERIC TRANSITION ISOTOPES; ISOTOPES; MATERIALS; METALS; MINUTES LIVING RADIOISOTOPES; NUCLEAR FUELS; NUCLEI; OXIDES; OXYGEN COMPOUNDS; POWER REACTORS; RADIOISOTOPES; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; SPONTANEOUS FISSION RADIOISOTOPES; THERMAL REACTORS; TRANSITION ELEMENT ALLOYS; URANIUM; URANIUM COMPOUNDS; URANIUM ISOTOPES; URANIUM OXIDES; WATER COOLED REACTORS; WATER MODERATED REACTORS; YEARS LIVING RADIOISOTOPES; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS