Fission power flattening in hybrid blankets using mixed fuel
Creators
- 1. The Scientific and Technical Research Council of Turkey, Emek is Hani Kat 15, Kizilay, Ankara (Turkey)
Description
In a source-driven fissionable blanket, a flat fission power density (FPD) is achieved by using a mixed fuel (ThO2 and natural UO2) with the thoriumuranium ratio changing from front to back in the ten fuel rows along the radial direction. A straightforward graphic method is used. The temporal behavior of the FPD has been observed for an operation period of 6 months and for a plant load factor of 75% by applying a fusion driver neutron flux of 1014 14-MeV neutrons(cm2 . s) at the first wall, corresponding to --2.25 MWm2. To keep the power density flat, it is necessary to replace the fuel in rows 1, 2, and 3, close to the first wall. The time intervals for this operation increase, counting from initial start-up, typically, 2 months, 6 months, etc. One result of this study is that plutonium produced in such a hybrid blanket contains very low amounts of even isotopic components even over very long operation times of --3 yr. Hence, if fusion reactors are introduced into the energy market, special regulations are needed for international safeguarding
Additional details
Publishing Information
- Journal Title
- Fusion Technol.
- Journal Volume
- 12
- Journal Issue
- 3
- Series
- Fusion Technol.
- Journal Page Range
- 395-408
- ISSN
- 0748-1896
- CODEN
- FUSTE
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 19074426
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY; S70: PLASMA PHYSICS AND FUSION TECHNOLOGY; S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Descriptors DEI
- FABRICATION; HYBRID REACTORS; ISOTOPE RATIO; NEUTRON FLUX FLATTENING; PLUTONIUM; SPECIFICATIONS; THORIUM OXIDES; URANIUM OXIDES
- Descriptors DEC
- ACTINIDE COMPOUNDS; ACTINIDES; CHALCOGENIDES; ELEMENTS; METALS; OXIDES; OXYGEN COMPOUNDS; THORIUM COMPOUNDS; TRANSURANIUM ELEMENTS; URANIUM COMPOUNDS