Proceedings of the ... International Conference on Radioactive Waste Management and Environmental RemediationAmerican Society of Mechanical Engineers,., 1997 - Nuclear facilities |
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Page 59
... tests to be carried out : a ) Reception and control area . b ) Manipulation cell : for the preparation of packages for leaching tests and for the extraction of test probes to determine their mechanical and radiological properties . The ...
... tests to be carried out : a ) Reception and control area . b ) Manipulation cell : for the preparation of packages for leaching tests and for the extraction of test probes to determine their mechanical and radiological properties . The ...
Page 415
... tests have characterized the large region ( in the order of 1 km3 ) loosely linked to small scale tracer tests . The flow - accounting test proposed here is a sort of hybrid offering the advantage of the speed of propaga- tion of ...
... tests have characterized the large region ( in the order of 1 km3 ) loosely linked to small scale tracer tests . The flow - accounting test proposed here is a sort of hybrid offering the advantage of the speed of propaga- tion of ...
Page 416
... tests , the region investigated is propor- tional to K / 0 ( where 0 is water filled porosity ) . Therefore for tests in the same rock with the same K , the sizes of investigation region should be as S to 0. For most rocks these ...
... tests , the region investigated is propor- tional to K / 0 ( where 0 is water filled porosity ) . Therefore for tests in the same rock with the same K , the sizes of investigation region should be as S to 0. For most rocks these ...
Contents
DESCRIPTIONS OF NATIONAL ENVIRONMENTAL MANAGEMENT PROGRAMS | 1 |
A Service to National Community in Chile | 11 |
Cora Project The Italian Way for Conditioning High and Low Level Liquid Radioactive Wastes | 23 |
Copyright | |
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acid actinides activity analysis assessment backfill bentonite borehole brine burnup calculated canister carbon CCDF cell cement cesium chemical coefficient compaction composition concentration containing criteria decommissioning decontamination disposal facility dose drums effect Energy environment environmental evaluation extraction flow geological glass groundwater hydraulic IAEA incineration ion exchange ion exchange resins level waste material measured ment neptunium Nirex nitric acid nuclear fuel nuclear power nuclides operation organic oxidation parameters performance permeability phase plant plutonium polonium potential production radiation radioactive contamination Radioactive Waste Management radionuclides radwaste reactor reduce release repository reprocessing resins risk rock safety salt samples scenarios Sellafield simulated solid solution sorbent sorption specific spent fuel storage surface Table tank technetium temperature tests tion transport treatment uranium vitrification volume waste disposal waste form waste management waste packages WIPP zirconolite zone