The International Atomic Energy Agency (IAEA) requires that all test and research reactors operating on Higher Enriched Uranium (HEU) should be converted to Low (LEU) for safety security purposes. Nigeria having a Miniature Neutron Source Reactor (MNSR) has been long interested in fuel technological not just develop the area but also meet with resolution nuclear treaty set out by global regulat...

Discriminators are described that quantify enhancements added to plutonium destruction and/or nuclear waste transmutation systems through use of an accelerator/fluid fuel combination. This combination produces a robust and flexible nuclear system capable of the destruction of all major long-lived actinides (including plutonium) and fission products. The discriminators discussed in this report a...

Transient fuel behavior in a Light Water-cooled Reactor core depends on nuclear properties (Doppler broadening, moderation ratio, and, sometimes, neutron gas temperature etc.) and variations of thermal-physics parameters (temperature distributions, elongation moderator density). Usually, rough reactor analysis one ignores the very details distributions largely staying frame so-called adiabatic ...

Molten-salt breeder reactors (MSBR's) are being developed by the Oak Ridge National Laboratory for generating low-cost power while extending the nation's resources of fissionable fuel. The fluid fuel in these reactors, consisting of UF4 and ThF4 dissolved in fluorides of beryllium and lithium, is circulated through a reactor core moderated by graphite. Technology developments over the past 20 y...

Monitoring of transuranic actinides (TRU–includes neptunium, plutonium, americium, and curium) during the separation of used nuclear fuel has been identified as a critical research area in the U.S. Advanced Fuel Cycle Research and Development program (AFC R&D). Recycling of used fuel by chemically separating it into uranium, fission products, and TRU would be the first step in this new fuel cyc...

One of the requirements of a future Fissile Material Cutoff Treaty is that fissile material used in naval reactor fuel must not be diverted for weapons purposes. This could become relevant for both weapon and non-weapon states of the NPT because, in both cases, the geometry of the fuel and core may be considered sensitive information. Inspections and measurements would therefore have to rely on...

This project will examine inert fuels containing ZrO2 and MgO as the inert matrix, with the relative amount of MgO varied from 30 % to 70 % in ZrO2. Reactor physics calculations will be used to examine suitable quantities of burnable poisons from the candidate elements Gd, Er, or Hf with reactor grade Pu providing the fissile component, with up to 10 % of Pu. Ceramics will be synthesized and ch...

Neutronic analysis on the Molten Salt Reactor FUJI-12 using fissile material 235U in LiF-BeF2-UF4 has been carried out. The problem faced use of thorium-based fuel is that amount 233U small and not available nature. was produced through 232Th breeding at a cost $46 million/kg. That very high price when compared to enrichment, which only $100/kg. MSR used this study generation IV reactor with mi...