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 88
... requirements in- cludes both marginal conditions prescribed in the li- cense and results of additional safety assessments which keep the above - mentioned framework . Accord- ing to this , at first sight , the Morsleben requirements ...
... requirements in- cludes both marginal conditions prescribed in the li- cense and results of additional safety assessments which keep the above - mentioned framework . Accord- ing to this , at first sight , the Morsleben requirements ...
Page 90
... Requirements for. i . Radiation Protection Group S1 S1 S2 S2 S2 S3 S3 S4 S5 The radioactive material is distributed ... requirements ( para 505-514 ) and , in addition , in case of IP - 2 the free drop test ( para 622 ) and the ...
... Requirements for. i . Radiation Protection Group S1 S1 S2 S2 S2 S3 S3 S4 S5 The radioactive material is distributed ... requirements ( para 505-514 ) and , in addition , in case of IP - 2 the free drop test ( para 622 ) and the ...
Page 91
... Requirements solid 3 fissile mass conc . < 50 g / 0.1 m3 Waste Form Groups : 01 Bitumen and plastic products 02 Solid matter 03 Metallic solid matter 04 Compacted waste 05 Cemented / concreted waste 06 Concentrates Radionuclide Specific ...
... Requirements solid 3 fissile mass conc . < 50 g / 0.1 m3 Waste Form Groups : 01 Bitumen and plastic products 02 Solid matter 03 Metallic solid matter 04 Compacted waste 05 Cemented / concreted waste 06 Concentrates Radionuclide Specific ...
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