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 197
... Concentration Table The Concentration Table provides another simple method for determining compliance and exemption from reporting by using measured concentrations of each nuclide in each stack . This worksheet may be used only if both ...
... Concentration Table The Concentration Table provides another simple method for determining compliance and exemption from reporting by using measured concentrations of each nuclide in each stack . This worksheet may be used only if both ...
Page 461
... Concentration ( M ) 104 10 : 5 10.6 GTM 3.1 107 GTM 3.0.1 Concentration ( Bq / mL ) 10 ' 10 ° 105 10 ' O 10 ° 109 • O Cm_aq_exp Cm_org exp Cm_aq ----- Cm_org 1 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 Stage Number Fig . 4 ...
... Concentration ( M ) 104 10 : 5 10.6 GTM 3.1 107 GTM 3.0.1 Concentration ( Bq / mL ) 10 ' 10 ° 105 10 ' O 10 ° 109 • O Cm_aq_exp Cm_org exp Cm_aq ----- Cm_org 1 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 Stage Number Fig . 4 ...
Page 656
... concentration , the removal of aluminum from solution takes place , and some equi- librium aluminum concentration is established . ( Fig . 2 , curves 2-3 ) . A comparison of the absolute concentrations of the silicon and aluminum ...
... concentration , the removal of aluminum from solution takes place , and some equi- librium aluminum concentration is established . ( Fig . 2 , curves 2-3 ) . A comparison of the absolute concentrations of the silicon and aluminum ...
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