Burning of the Minor Actinides in fuel cycle of the MTR-reactors
Creators
Description
Highlights: • Re-cycling of the ETRR-2 core by the UO2 caramel fuel. • Re-cycling of the ETRR-2 core by the MOX mixed with some actinides was made. • Neutronic parameters of the studied fuels were calculated and compared. • Reduction of the 235U mass loaded in the ETRR-2 core was realized. • Power peaking factors of the studied fuels were calculated and compared. - Abstract: A computational study to recycle the spent fuel of the MTR-22 MW reactor by MOX (UO2 and PuO2) caramel fuel (CF) mixed with 237Np, 241Am, 242mAm, 243Am and 245Cm as burnable absorber actinides has been performed. The calculation results showed that the enrichment with 235U and the loaded amount of the 235U uranium decreases significantly up to 33%. A re-evaluation of the criticality, the neutronic parameters, and the power peaking factors for the MTR-22 MW reactor for the MOX CF mixed with the 237Np, 241Am, 242mAm, 243Am and 245Cm actinides was done. The obtained results showed that re-cycling the spent fuel of MTR-22 MW reactor by MOX CF mixed with 0.01% (237Np, 241Am, 242mAm, 243Am and 245Cm) actinides has no negative effects on the safety of the reactor. In addition re-cycling the plutonium and the 237Np, 241Am, 242mAm, 243Am and 245Cm actinides together leads to less hazardous and possibly more useful forms of the radioactive wastes, and enhances the proliferation resistance of the fissile materials.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.anucene.2016.10.017Additional details
Identifiers
- DOI
- 10.1016/j.anucene.2016.10.017;
- PII
- S0306-4549(16)30959-8;
Publishing Information
- Journal Title
- Annals of Nuclear Energy (Oxford)
- Journal Volume
- 100
- Journal Issue
- Part 2
- Journal Page Range
- p. 119-127
- ISSN
- 0306-4549
- CODEN
- ANENDJ
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 48085507
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Descriptors DEI
- AMERICIUM 241; AMERICIUM 242; AMERICIUM 243; COMPARATIVE EVALUATIONS; CRITICALITY; CURIUM 245; ETRR-2 REACTOR; FISSILE MATERIALS; FUEL CYCLE; MTR REACTOR; NEPTUNIUM 237; PLUTONIUM; PLUTONIUM OXIDES; RADIOACTIVE WASTES; REACTOR SAFETY; SPENT FUELS; URANIUM 235; URANIUM DIOXIDE
- Descriptors DEC
- ACTINIDE COMPOUNDS; ACTINIDE NUCLEI; ACTINIDES; ALPHA DECAY RADIOISOTOPES; AMERICIUM ISOTOPES; BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; CHALCOGENIDES; CURIUM ISOTOPES; ELECTRON CAPTURE RADIOISOTOPES; ELEMENTS; ENERGY SOURCES; ENRICHED URANIUM REACTORS; EVALUATION; EVEN-ODD NUCLEI; FISSIONABLE MATERIALS; FUELS; HEAVY NUCLEI; HOURS LIVING RADIOISOTOPES; INTERNAL CONVERSION RADIOISOTOPES; IRRADIATION REACTORS; ISOMERIC TRANSITION ISOTOPES; ISOTOPES; MATERIALS; MATERIALS TESTING REACTORS; METALS; MINUTES LIVING RADIOISOTOPES; NANOSECONDS LIVING RADIOISOTOPES; NEPTUNIUM ISOTOPES; NUCLEAR FUELS; NUCLEI; ODD-EVEN NUCLEI; ODD-ODD NUCLEI; OXIDES; OXYGEN COMPOUNDS; PLUTONIUM COMPOUNDS; POOL TYPE REACTORS; RADIOACTIVE MATERIALS; RADIOISOTOPES; REACTOR MATERIALS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SAFETY; SPONTANEOUS FISSION RADIOISOTOPES; TANK TYPE REACTORS; THERMAL REACTORS; TRANSURANIUM COMPOUNDS; TRANSURANIUM ELEMENTS; URANIUM COMPOUNDS; URANIUM ISOTOPES; URANIUM OXIDES; WASTES; WATER COOLED REACTORS; WATER MODERATED REACTORS; YEARS LIVING RADIOISOTOPES
Optional Information
- Copyright
- Copyright (c) 2016 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.