Multi-recycling of actinides in thorium based fuels
Creators
- 1. Delft University of Technology, Interfaculty Reactor Institute - IRI, Mekelweg 15, NL-2629 JB Delft (Netherlands)
- 2. NRG, P.O. Box 25 NL-1755 ZG Petten (Netherlands)
Description
Burnup calculations have been performed to assess reactor physics and waste toxicity characteristics of a PWR fuelled with either low enriched UO2 (LEU) fuel, medium enriched UO2 (MEU) fuel mixed in ThO2, or highly enriched UO2 (HEU) fuel mixed in ThO2. For all fuels the reactivity coefficients have been calculated as a function of burnup, and the radiotoxicity curves of the spent fuels and loss fractions as a function of storage time. Without recycling, the fuel temperature coefficient of the MEU fuel is strongest negative due to the large quantities of both 238U and 232Th in the fuel. For the HEU fuel, the moderator temperature coefficient is very small negative or even positive, which means that special measures have to be taken. Up to 20,000 years of storage, the radiotoxicity of HEU spent fuel is lowest and that of LEU spent fuel largest. After this period the reverse is true. After two times recycling of Pa+U in MEU fuel, the radiotoxicity of the reprocessing losses is a factor of 2 less than the radiotoxicity of the LEU spent fuel. If in addition Pu is recycled in MEU fuel, the reduction factor equals a factor of 5 to 10. The highest reduction (a factor of 10 to 20) can be obtained when Pa and U are recycled in HEU fuel. Only in this case, the reduction factor is significantly larger than that obtained with recycling of Pu in standard (U,Pu) MOX fuel. In general, multi-recycling worsens the reactivity coefficients with several tens of percents
Additional details
Publishing Information
- Publisher
- American Nuclear Society - ANS
- Imprint Place
- Jackson Hole, Wyoming (United States)
- Imprint Pagination
- 8 p.
Conference
- Title
- International Conference on Future Nuclear Systems - Nuclear Technology - Bridging the Millennia
- Acronym
- Global'99
- Dates
- 29 Aug - 3 Sep 1999
- Place
- Las Vegas, NV (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 53059289
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS; S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BURNUP; HIGHLY ENRICHED URANIUM; MIXED OXIDE FUELS; MODERATORS; PWR TYPE REACTORS; RADIOACTIVE WASTES; REACTOR PHYSICS; RECYCLING; REPROCESSING; SAFETY STANDARDS; SPENT FUELS; TEMPERATURE COEFFICIENT; THORIUM; THORIUM 232; THORIUM OXIDES; TOXICITY; URANIUM 238; URANIUM DIOXIDE
- Descriptors DEC
- ACTINIDE COMPOUNDS; ACTINIDE NUCLEI; ACTINIDES; ALPHA DECAY RADIOISOTOPES; CHALCOGENIDES; ELEMENTS; ENERGY SOURCES; ENRICHED URANIUM; ENRICHED URANIUM REACTORS; EVEN-EVEN NUCLEI; FUELS; HEAVY NUCLEI; ISOTOPE ENRICHED MATERIALS; ISOTOPES; MATERIALS; METALS; NUCLEAR FUELS; NUCLEI; OXIDES; OXYGEN COMPOUNDS; PHYSICS; POWER REACTORS; RADIOACTIVE MATERIALS; RADIOISOTOPES; REACTIVITY COEFFICIENTS; REACTOR MATERIALS; REACTORS; SEPARATION PROCESSES; SOLID FUELS; SPONTANEOUS FISSION RADIOISOTOPES; STANDARDS; THERMAL REACTORS; THORIUM COMPOUNDS; THORIUM ISOTOPES; URANIUM; URANIUM COMPOUNDS; URANIUM ISOTOPES; URANIUM OXIDES; WASTES; WATER COOLED REACTORS; WATER MODERATED REACTORS; YEARS LIVING RADIOISOTOPES
Optional Information
- Notes
- 6 refs.; available from American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (US)