Scientific Basis for Nuclear Waste Management XXIX: Symposium Held September 12-16, 2005, Ghent, BelgiumPierre Van Iseghem |
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Page 392
... Proc.127 ) , p.97 ( 1989 ) . [ 2 ] N.Godon and E.Vernaz in Scientific Basis for Nuclear Waste Management XIII ( Mater . Res . Soc . Symp.Proc . 176 ) , p.319 ( 1990 ) . [ 3 ] Y.Inagaki , R.Saito , H.Furuya , K.Idemitsu and T.Arima in ...
... Proc.127 ) , p.97 ( 1989 ) . [ 2 ] N.Godon and E.Vernaz in Scientific Basis for Nuclear Waste Management XIII ( Mater . Res . Soc . Symp.Proc . 176 ) , p.319 ( 1990 ) . [ 3 ] Y.Inagaki , R.Saito , H.Furuya , K.Idemitsu and T.Arima in ...
Page 912
... Proc . 294 , Pittsburgh , PA , 1993 ) , pp.467-474 . 3. H. Sato , T. Ashida , Y. Kohara , and M. Yui , ibid , pp.430-435 . 4. H. Sato , M. Yui , and H. Yoshikawa , ibid , XVIII , edited by T. Murakami and R. C. Ewing , ( Mater . Res ...
... Proc . 294 , Pittsburgh , PA , 1993 ) , pp.467-474 . 3. H. Sato , T. Ashida , Y. Kohara , and M. Yui , ibid , pp.430-435 . 4. H. Sato , M. Yui , and H. Yoshikawa , ibid , XVIII , edited by T. Murakami and R. C. Ewing , ( Mater . Res ...
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... Proc . 333 , Pittsburgh , PA , 1994 ) , pp.939-946 . Y. Kuroda , K. Idemitsu , H. Furuya , Y. Inagaki and T. Arima in Scientific Basis for Nuclear Waste Management XX , edited by W.J. Gray and I.R. Triay ( Mater . Res . Soc . Proc . 465 ...
... Proc . 333 , Pittsburgh , PA , 1994 ) , pp.939-946 . Y. Kuroda , K. Idemitsu , H. Furuya , Y. Inagaki and T. Arima in Scientific Basis for Nuclear Waste Management XX , edited by W.J. Gray and I.R. Triay ( Mater . Res . Soc . Proc . 465 ...
Contents
Underground | 3 |
The JNC Generic URL Research ProgramProviding | 13 |
Development of the Supercontainer Design for Deep Geological | 23 |
Copyright | |
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2006 Materials Research acid actinides alteration americium analysis assessment behaviour bentonite Boom Clay buffer calcite calculated canister carbon cations cement chemical Coffinite composition concentration concrete container corrosion products corrosion rate decrease developed diffusion coefficient disposal dissolution rate effect electron elements environment ethanol experimental experiments Figure formation fraction fracture geological glass dissolution groundwater grout host rock increase initial ions irradiation layer leaching magnetite Materials Research Society matrix measured metal minerals montmorillonite Nuclear Waste obtained overpack oxidation parameters pellet performed permeability phase pore porosity potential precipitation predicted pressure Proc processes pyrochlore radioactive waste radionuclides ratio reaction redox release repository samples saturation silica silicic acid simulated slurry smectite solid solubility solution sorption specimen spent fuel steel structure surface Symp Table temperature tests tracer values waste form Waste Management waste package zeolite zirconolite