Analysis of Burnup effects and Its Integrity Assessment in the Interim of Irradiation with Molecular Dynamics
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MRS Advances © 2020 Materials Research Society DOI: 10.1557/adv.2020.19
Analysis of Burnup effects and Its Integrity Assessment in the Interim of Irradiation with Molecular Dynamics Ahli K.D. Williea,
Hongtao Zhaoa,b*, M. Mustafa Azeema , Teplinskaya Svetlanac
a Fundamental Science on Nuclear Safety and Simulation Technology Laboratory, Harbin Engineering University, Harbin, 150001, China
b
Institute of Technical Physics, Heilongjiang Academy of Sciences 150086
c
College of Material Science and Chemical Engineering, Harbin Engineering University, Harbin, 150001, China
A b s t r a c t:
Burnups can cause major structural changes in the edge of the fuel rod and a general degradation of the thermal conductivity. In irradiated mixed oxide fuels of UO2, PuO2 with NpO2 as fission products (FP) various chemical states depending on the conditions of the fuel is developed. This work, we firstly applied the MD relation to obtain the thermal conductivity of UO2, PuO2, and (U, Pu) O2 in temperature range of 300–2000 K. Lattice parameter, Burnup and the thermal conductivity were then calculated for specified UO 2 and PuO2. This calculation relates the degradation of thermal conductivity with a number of pores and increasing temperature. Finally, the migration energy barrier and the recovery energies of the obstruction type defects were calculated with molecular dynamics simulation. Key words: burnup, Molecular dynamics, thermal conductivity
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INTRODUCTION During the operation of a nuclear reactor, the structural materials are exposed to high levels of radiation doses and high temperatures during their operational lifetime in reactors [1-7]. Uranium-base fuel results in changes in the composition of the fuel system due to loss of fissionable materials as a result of fission and the buildup of fission products. Subjecting the mixed oxide (MOX) fuel in-reactor environment leads to microstructural changes due to the evolution of radiation produced defects, segregation and precipitation of fission products, and mechanical deformation. Consequently, little minor actinide (Np, Am, Cm) elements are generated due to the process of neutron capture and the transmutation products which will influence the thermal properties of mixed oxide fuels in turn. In view of reactor fuel property evaluation, over the past decade there has been increased international recognition of the need for expanded, high quality, public sources of burnup data to validate the U-MOX spent fuel calculations [8]. Measurement of thermal properties under high temperature conditions is difficult to perform because of the cost of expensive appliances and materials as well as the extensive safety precautions, though it is important to evaluate comprehensively the thermal properties of mixed oxide fuel
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