Proceedings of the ... International Conference on Radioactive Waste Management and Environmental Remediation, Volume 1American Society of Mechanical Engineers, 1995 - Nuclear facilities |
From inside the book
Results 1-3 of 71
Page 331
... temperature and the outside air and ground temperatures are all assumed to be constant and uniform ( see Modeling Assumptions ) . All walls and floors of the SFP are flat . Therefore , the one - dimensional flat - plate heat conduction ...
... temperature and the outside air and ground temperatures are all assumed to be constant and uniform ( see Modeling Assumptions ) . All walls and floors of the SFP are flat . Therefore , the one - dimensional flat - plate heat conduction ...
Page 332
... temperature ; e ) Knowing the initial and final SFP temperatures which define each period between quasi - static outside ambi- ent conditions , and the heat - up rate at the final SFP temperature , solve for the amount of time required ...
... temperature ; e ) Knowing the initial and final SFP temperatures which define each period between quasi - static outside ambi- ent conditions , and the heat - up rate at the final SFP temperature , solve for the amount of time required ...
Page 768
... TEMPERATURE CALCULATIONS Calculations for long - term temperature development at sev- eral significant sampling points , e.g. at the container and cask surfaces , have been performed with the computer code LIN- SOURPREPOST ( 5 ) to ...
... TEMPERATURE CALCULATIONS Calculations for long - term temperature development at sev- eral significant sampling points , e.g. at the container and cask surfaces , have been performed with the computer code LIN- SOURPREPOST ( 5 ) to ...
Contents
VOLUME | 1 |
Evaluation of Possible Treatment of Solid Raw Containing Polymer with High Frequency Heating | 5 |
Volume ReductionPellet Handling PressSystems for Supercompaction of Dry Solid Low and Intermediate | 10 |
Copyright | |
30 other sections not shown
Other editions - View all
Common terms and phrases
acid actinides activities americium assessment BNFL boreholes borosilicate glass burnup calculated CANDU canister cask cesium chemical composition concentration containing cost developed disposal facility disposition dose rate Energy environment environmental evaluation fissile materials fission fission products fuel assemblies fuel cycle fuel elements geological glass Gorleben groundwater Hanford heat high level HLLW IAEA impact interim storage ions irradiated Laboratory leaching level waste licensing loading measured melt melter ment metal monitoring MOX fuel neptunium neutron nuclear fuel nuclear power nuclide operation options oxide Pantex parameters performed phase plant plutonium potential production radiation radionuclides radwaste reactor recycling regulatory release repository reprocessing requirements risk ruthenium safety salt salt dome samples scenario simulated solution spent fuel surface Table tank technical temperature tion transport tritium uranium vitrified Waste Management waste packages weapons