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 215
... temperature on the accumulation of creep strain . Internal pressure at T = 20 C , MPa Fig . 4. Maximum allowable temperature of RBMK - 1000 spent fuel as a function of internal rod pressure . MATERIALS SCIENCE CHALLENGES IN LONG - TERM ...
... temperature on the accumulation of creep strain . Internal pressure at T = 20 C , MPa Fig . 4. Maximum allowable temperature of RBMK - 1000 spent fuel as a function of internal rod pressure . MATERIALS SCIENCE CHALLENGES IN LONG - TERM ...
Page 286
... temperature range : Ea is equal to 75 kJ / mol below 1100 ° C , 360 kJ / mol above this temperature in their steady state release experiments ( 19 ) . The author suggests that , at high tem- perature , helium diffuses as bubbles by a ...
... temperature range : Ea is equal to 75 kJ / mol below 1100 ° C , 360 kJ / mol above this temperature in their steady state release experiments ( 19 ) . The author suggests that , at high tem- perature , helium diffuses as bubbles by a ...
Page 456
... Temperature Change Fig . 2. Experimental configuration ( left ) and photo of the test set - up in Experiments I through IV ( right ) . Heat conductivity measurements for moist rock salt at homogenous vertical temperature gradient was ...
... Temperature Change Fig . 2. Experimental configuration ( left ) and photo of the test set - up in Experiments I through IV ( right ) . Heat conductivity measurements for moist rock salt at homogenous vertical temperature gradient was ...
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