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Aerospace Nuclear Science & Technology
Organized to promote the advancement of knowledge in the use of nuclear science and technologies in the aerospace application. Specialized nuclear-based technologies and applications are needed to advance the state-of-the-art in aerospace design, engineering and operations to explore planetary bodies in our solar system and beyond, plus enhance the safety of air travel, especially high speed air travel. Areas of interest will include but are not limited to the creation of nuclear-based power and propulsion systems, multifunctional materials to protect humans and electronic components from atmospheric, space, and nuclear power system radiation, human factor strategies for the safety and reliable operation of nuclear power and propulsion plants by non-specialized personnel and more.
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Latest News
Norway’s Halden reactor takes first step toward decommissioning
The government of Norway has granted the transfer of the Halden research reactor from the Institute for Energy Technology (IFE) to the state agency Norwegian Nuclear Decommissioning (NND). The 25-MWt Halden boiling water reactor operated from 1958 to 2018 and was used in the research of nuclear fuel, reactor internals, plant procedures and monitoring, and human factors.
Guangwen Bi, Shengyi Si, Chanyun Liu
Nuclear Technology | Volume 183 | Number 3 | September 2013 | Pages 308-320
Technical Paper | Fission Reactors | doi.org/10.13182/NT13-A19420
Articles are hosted by Taylor and Francis Online.
This work is focused on core design, spent-fuel characteristics assessment, and fuel cycle analysis for thorium-uranium breeding recycle in a typical pressurized water reactor (PWR), without any major change to the fuel lattice and the core internals but substituting the uranium oxide (UOX) pellet with a thorium-based fuel pellet. Two mixed cores are investigated, one loaded with mixed reactor-grade plutonium-thorium oxide (PuThOX) fuel assemblies and the other with mixed reactor-grade 233U-thorium oxide (U3ThOX) fuel assemblies. The high purity of reactor-grade 233U extracted from burnt PuThOX fuel is used as seeds of U3ThOX for starting thorium-uranium breeding recycle.The core design and analysis indicated that thorium-uranium breeding recycle is technically feasible in current PWRs. In the mixed core with U3ThOX loading, the well-designed U3ThOX assemblies were located on the periphery of the core as a "blanket" region, which remain in core for six cycles and get breeding with 232Th-233U. The feedback parameters and kinetic parameters are dominated by the UOX fuel in the inner core. For the UOX/PuThOX mixed core, the higher plutonium content leads to harder neutron spectrum, smaller reactivity worth of neutron absorbers, and smaller delayed neutron fraction and prompt neutron lifetime, which are similar to the current mixed cores partially loaded with the plutonium-uranium mixed-oxide (MOX) fuel.The fuel cycle analysis has shown that 233U monorecycling with U3ThOX fuel could save 13% of natural uranium resource compared with UOX once-through fuel cycle, slightly more than that of plutonium monorecycling with MOX fuel. If 233U multirecycling with U3ThOX fuel is implemented, more natural uranium resource would be saved.
