Proceedings of the ... International Conference on Radioactive Waste Management and Environmental Remediation, Volumes 1-3American Society of Mechanical Engineers,., 2002 - Nuclear facilities |
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Page 204
... Irradiated : 2 Cycles ( 29 Gwd / tU ) 14 ⚫ irradiated : 4 Cycles ( 49 Gwd / tU ) 1,2 1 0,8 0,6 0,4 0.2 0 o 50 100 150 200 250 Time ( hours ) Hoop Strain ( % ) 0,8 0,6 0,4 Creep Law 0.2 0 % - 0 , = 200 MPa - Bu = 46 GWd / tU ( 4 cycles ) ...
... Irradiated : 2 Cycles ( 29 Gwd / tU ) 14 ⚫ irradiated : 4 Cycles ( 49 Gwd / tU ) 1,2 1 0,8 0,6 0,4 0.2 0 o 50 100 150 200 250 Time ( hours ) Hoop Strain ( % ) 0,8 0,6 0,4 Creep Law 0.2 0 % - 0 , = 200 MPa - Bu = 46 GWd / tU ( 4 cycles ) ...
Page 275
... irradiated and irradiated , to compare and to analyse the difference between these two types of fuel . The weight gain curves show a different behaviour depending on irradiation : non - irradiated MOX is less oxi- dised than UOX , but ...
... irradiated and irradiated , to compare and to analyse the difference between these two types of fuel . The weight gain curves show a different behaviour depending on irradiation : non - irradiated MOX is less oxi- dised than UOX , but ...
Page 287
... irradiated from 7 to 64 GWd / tm , have shown that helium release was greater than that of fission gases in low or un - pressurised rods ( 28 ) . Qualitatively speaking , this means that the diffusion of helium is significantly greater ...
... irradiated from 7 to 64 GWd / tm , have shown that helium release was greater than that of fission gases in low or un - pressurised rods ( 28 ) . Qualitatively speaking , this means that the diffusion of helium is significantly greater ...
Contents
REMEDIATION OF URANIUM MINING AND MILLING SITES | 1 |
DISPOSAL SITE CHARACTERIZATION | 2 |
Transparency and Public Participation | 15 |
Copyright | |
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activities Agency AMEC approach assessment Atomic CBFO CE marking chemical cladding cleanup clearance levels concentration containers cost creep criteria decision decommissioning decontamination deep geological repository Department of Energy disposal facilities dose environment Environmental Remediation European European Commission evaluation exposure fission fission products fuel rod geological disposal hazards helium IAEA implementation industry interim storage inventory irradiated issues Laboratory long-term Management and Environmental material ment MOX fuels National needs nuclear power nuclides operation options oxidation peer review planning plant potential principles problem radiation radioactive waste management radiological radionuclides Radon reactor recycling regulations regulatory release reprocessing requirements risk Russian safety scenarios solution sources specific spent fuel spent nuclear fuel stakeholder strategy surface technical temperature tests Thematic Network tion transport U.S. Department uranium uranium dioxide USNRC WIPP Yucca Mountain