Oxidation and hydrolysis of thorium doped uranium nitride fuel for use in LWR

• Influence of thorium content on oxidation resistance UN was observed Thorium improve the low porosity pellets in air Uranium nitride sintered SPS can withstand interaction with water at 100°C Loss pellet integrity 200°C, regardless doping Phase separation ThO 2 and UO measured after exposure experiment is being investigated as a replacement for it shows enhanced thermal properties seems to be promising accident tolerant fuel (ATF) candidate. The main drawback its innate air/water environments. This becomes challenge implementation water-cooled reactors. effect stability uranium microspheres by spark plasma sintering (SPS) oxidizing environments using thermogravimetric analysis autoclave testing. It found that during density had noticeable effect, increasing reaction onset temperatures higher densities. In addition, improved maximal rate temperature approximately 50 K. However, this almost nonexistent highly porous doped microspheres. 373 K showed manufactured survive unchanged least six hours boiling water, which an improvement cold-pressed pellets. At 473 573 K, were oxidized disintegration into oxide powder observed. Thorium-doped did not present any respect these temperatures.