Characterization Of Cladding Hull Wastes From Used Nuclear Fuels

Archives of Metallurgy and Materials

S.-M. Hwang¹  G.I. Park²  S.Y. Han²  M.K. Jeon²  K.H. Kang²  C.H. Lee² 

[1] HYDROGEN AND FUEL CELL DEPARTMENT, KOREA INSTITUTE OF ENERGY RESEARCH, 152, GAJEONG-RO, YUSEONG-GU, DAEJEON 305-343, REPUBLIC OF KOREA;NUCLEAR FUEL CYCLE PROCESS PROCESS DEVELOPMENT DIVISION, KOREA ATOMIC ENERGY RESEARCH INSTITUTE, 989-11 DAEDEOK-DAERO, YUSEONG-GU, DAEJEON 305-353, REPUBLIC OF KOREA

关键词: Keywords: Used nuclear fuels;    Metal wastes;    Cladding hulls;    Zircaloy;    Radioactivity;   

DOI  :  10.1515/amm-2015-0097

学科分类：金属与冶金

来源: Akademia Gorniczo-Hutnicza im. Stanislawa Staszica / University of Mining and Metallurgy

【 摘 要 】

Used cladding hulls from pressurized water reactor (PWR) are characterized to provide useful information for the treatment and disposal of cladding hull wastes. The radioactivity and the mass of gamma emitting nuclides increases with an increase in the fuel burn-up and their removal ratios are found to be more than 99 wt.% except Co-60 and Cs-137. In the result of measuring the concentrations of U and Pu included in the cladding hull wastes, most of the residues are remained on the surface and the removal ratio of U and Pu are revealed to be over 99.98 wt.% for the fuel burn-up of 35,000 MWd/tU. An electron probe micro-analyzer (EPMA) line scanning shows that radioactive fission products are penetrated into the Zr oxide layer, which is proportional to the fuel burn-up. The oxidative decladding process exhibits more efficient removal ratio of radionuclides.

【 授权许可】

Unknown