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 390
... simulated nonradioactive HLLW is shown in Table I. The radio- active HLLW was obtained from the storage tank of ... Simulated Nonradioactive HLLWa and Radioactive HLLWb Element Na Fe Simulated Nonradioactive HLLW ( g / l ) An ...
... simulated nonradioactive HLLW is shown in Table I. The radio- active HLLW was obtained from the storage tank of ... Simulated Nonradioactive HLLWa and Radioactive HLLWb Element Na Fe Simulated Nonradioactive HLLW ( g / l ) An ...
Page 391
... simulated non- radioactive HLLW by electrolytic method . to nitric acid was 2 : 1 , and the volume of the HLLW was 0.31 . The pH value of the simulated nonradioactive HLLW increased when formic acid was added for the denitration ...
... simulated non- radioactive HLLW by electrolytic method . to nitric acid was 2 : 1 , and the volume of the HLLW was 0.31 . The pH value of the simulated nonradioactive HLLW increased when formic acid was added for the denitration ...
Page 496
... simulated fuel and simulated spent fuel of ThO2 - Al2O3 - MgO system prepared at 1400ÉC under low oxygen potentials . ( 1 ) : Simulated fuel consisting of fluorite + spinel + corundum with a composition of 26mol % ThO2 + 63mol % Al2O3 + ...
... simulated fuel and simulated spent fuel of ThO2 - Al2O3 - MgO system prepared at 1400ÉC under low oxygen potentials . ( 1 ) : Simulated fuel consisting of fluorite + spinel + corundum with a composition of 26mol % ThO2 + 63mol % Al2O3 + ...
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