Proceedings of the ... International Conference on Radioactive Waste Management and Environmental Remediation, Volume 1American Society of Mechanical Engineers, 1995 - Nuclear facilities |
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Page 169
... measured rela- tionship between potassium - 40 and total potassium , and led to a loss of confidence in the measured results . These measurement problems had their greatest effect on samples containing low concentrations of potassium ...
... measured rela- tionship between potassium - 40 and total potassium , and led to a loss of confidence in the measured results . These measurement problems had their greatest effect on samples containing low concentrations of potassium ...
Page 267
... measured at various positions of a CASTOR cask filled with maximum burnup THTR fuel ele- ments . Measurements of the neutron dose rate at the loaded transport and storage cask after inserting the primary and secon- dary lid , as well as ...
... measured at various positions of a CASTOR cask filled with maximum burnup THTR fuel ele- ments . Measurements of the neutron dose rate at the loaded transport and storage cask after inserting the primary and secon- dary lid , as well as ...
Page 784
... measured stress values to rock zones located further from the drifts initial vertical stress of approx . 12 MPa can be estimated . Comparing the measured rock stress to the theoretical over- burden pressure of about 18 MPa , a generally ...
... measured stress values to rock zones located further from the drifts initial vertical stress of approx . 12 MPa can be estimated . Comparing the measured rock stress to the theoretical over- burden pressure of about 18 MPa , a generally ...
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 | |
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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