Proceedings of the ... International Conference on Radioactive Waste Management and Environmental RemediationAmerican Society of Mechanical Engineers,., 1997 - Nuclear facilities |
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Page 73
... doses of external irradia- tion have been registered in N.Shepelichi ( 19.2 mSv - year ' ) , they are in 12-27 times greater than the doses recorded in other foriestries . Due to the inhalation way of plutonium irradiation the dose for ...
... doses of external irradia- tion have been registered in N.Shepelichi ( 19.2 mSv - year ' ) , they are in 12-27 times greater than the doses recorded in other foriestries . Due to the inhalation way of plutonium irradiation the dose for ...
Page 130
... dose ( or risk ) resulting from the contamination left behind after cleanup . In intervention situations , optimisation is aimed at the derivation of the intervention or action levels ( in terms of averted dose ) before any cleanup was ...
... dose ( or risk ) resulting from the contamination left behind after cleanup . In intervention situations , optimisation is aimed at the derivation of the intervention or action levels ( in terms of averted dose ) before any cleanup was ...
Page 845
... dose equivalent rate in the distance of 1 m from RPV outside surface are very similar . 3,5E + 06 3,0E + 06 Dose equivalent rate from core basket 1,8E + 04 1,6E + 04 1,4E + 04 1,2E + 04 1,0E + 04 8,0E + 03 6,08 + 03 Total dose ...
... dose equivalent rate in the distance of 1 m from RPV outside surface are very similar . 3,5E + 06 3,0E + 06 Dose equivalent rate from core basket 1,8E + 04 1,6E + 04 1,4E + 04 1,2E + 04 1,0E + 04 8,0E + 03 6,08 + 03 Total dose ...
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