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Results 1 to 25 of 183

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Management with HLW providing a minimal diffusion of their elements in the system matrix-solution-rockZYRYANOV, V; KOTELNIKOV, A.International geological congress. 1992, p.921Conference Paper

The Application of Quadtree Algorithm to Information Integration for Geological Disposal of High-level Radioactive WasteMIN GAO; SHUTAO HUANG; XIA ZHONG et al.Proceedings of SPIE, the International Society for Optical Engineering. 2010, Vol 7840, issn 0277-786X, isbn 978-0-8194-8363-8, 784014.1-784014.7Conference Paper

Site investigation for disposal of high-level radioactive wastes under the seabed : possibilities of new decisions and methodsPISKAREV, A.L.International geological congress. 1992, p.918Conference Paper

En Japonais = Geologic disposal of high-level radioactive waste -studies in the Geological Survey of Japan during 1985-1989KOIDE, H; MATSUHISA, Y; SAKAMAKI, Y et al.1991, Vol 42, Num 5, pp 233-234, issn 0016-7665Article

En Japonais = Research on underground disposal of high-level radioactive waste (I)1991, Vol 42, Num 5, pp 233-287, issn 0016-7665Article

Rock mechanic considerations in designing a nuclear waste repository in hard rockHARDY, M.P; BAUER, S.J.U.S. rock mechanics symposium. 1992, pp 1041-1050Conference Paper

En Japonais = Natural setting of Japanese islands and geologic disposal of high-level wasteKOIDE, H.1991, Vol 42, Num 5, pp 235-248, issn 0016-7665Article

Technical design and rock engineering of the Finnish high level nuclear waste repositoryRIEKKOLA, R; SALO, J.-P.International Congress on Rock MechanicsCongrès International de Mécanique des RochesInternationaler Kongress über Felsmechanik. 1999, pp 51-55, isbn 90-5809-069-8Conference Paper

Migration des gaz et pression de rupture dans une argile compactée destinée à la barrière ouvragée d'un stockage profond = Gas migration and breakthrough pressure in a compacted clay for engineered barrier of a deep disposalGALLE, C.Bulletin de la Société géologique de France. 1998, Vol 169, Num 5, pp 675-680, issn 0037-9409Article

Microstructure and micro/macro-diffusion behavior of tritium in bentoniteICHIKAWA, Y; KAWAMURA, K; FUJII, N et al.Applied clay science. 2004, Vol 26, Num 1-4, pp 75-90, issn 0169-1317, 16 p.Conference Paper

Modeling of geological environment for performance assessmentSAKUMA, H.International geological congress. 1992, p.919Conference Paper

Analysis of disposal tunnel for high-level radioactive waste by micromechanics-based continuum modelYOSHIDA, H; HORII, H; KANEKO, T et al.U.S. Rock Mechanics Symposium, DC Rocks 2001. 2001, pp 551-558, isbn 90-2651-836-6, 8 p.Conference Paper

Rôle de la teneur en silice dissoute sur l'environnement de Zr et de Fe lors de l'altération du verre nucléaire R7T7 = Role of the content in dissolved silica on the environment of Zr and Fe during the alteration of the R7T7 nuclear glassPELEGRIN, E; ARRIO, M. A; FLANCK, A. M et al.Réunion des Sciences de la Terre. 1998, p. 172Conference Paper

Hydrothermal equipments and tests of chemical durability for glassYANAGISAWA, F.1992, Vol 42, Num 236, pp 415-422, issn 0918-2454Article

En Japonais = Research on underground disposal of high-level radioactive waste. II1991, Vol 42, Num 6-7, pp 289-347, issn 0016-7665Article

Models, validation, and applied geochemistry: Issues in science, communication, and philosophyKIRK NORDSTROM, D.Applied geochemistry. 2012, Vol 27, Num 10, pp 1899-1919, issn 0883-2927, 21 p.Conference Paper

Dispersion of radionuclides around the new nuclear Oklo reactors (Gabon) : implications for high-level radioactive waste disposalHEMOND, C; MENAGER, M.-T; MENET, C et al.International geological congress. 1992, p.919Conference Paper

Single-pass flow-through test elucidation of weathering behavior and evaluation of contaminant release models for Hanford tank residual radioactive wasteCANTRELL, Kirk J; CARROLL, Kenneth C; BUCK, Edgar C et al.Applied geochemistry. 2013, Vol 28, pp 119-127, issn 0883-2927, 9 p.Article

Maximum and Minimum Principles for Radionuclide Transport Calculations in Geological Radioactive Waste Repository: Comparison Between a Mixed Hybrid Finite Element Method and Finite Volume Element discretizationsGENTY, Alain; LE POTIER, Christophe.Transport in porous media. 2011, Vol 88, Num 1, pp 65-85, issn 0169-3913, 21 p.Article

A study on the thermal conductivity of compacted bentonitesTANG, Anh-Minh; CUI, Yu-Jun; LE, Trung-Tinh et al.Applied clay science. 2008, Vol 41, Num 3-4, pp 181-189, issn 0169-1317, 9 p.Article

Geochemicky program k projektu hlubiného uloziste vysoce radioaktivnich odpadu = Geochemical programme of the High-level Waste Isolation ProjectPRIMAS, M.Časopis pro mineralogii a geologii. 1993, Vol 38, Num 1-2, pp 118-122, issn 0008-7378Article

High-level waste disposal, ethics and thermodynamicsSCHWARTZ, Michael O.Environmental geology (Berlin). 2008, Vol 54, Num 7, pp 1485-1488, issn 0943-0105, 4 p.Article

Incertitude temporelle et controverse territoriale : Expérimentation politique et scientifique dans la gestion des déchets radioactifs à vie longue = Temporal uncertainty and territorial controversy : Political and scientifical experiment in the high level radioactive waste managementBARTHE, Y.Programme environnement, vie et sociétés. Journées. 1997, pp 235-242, 2VolConference Paper

Application of FLAC3D on HLW underground repository concept developmentKWON, S; PARK, J. H; CHOI, J. W et al.International FLAC symposium. 2003, pp 145-152, isbn 90-5809-581-9, 8 p.Conference Paper

Thermo-mechanical effects around a radioactive waste repositoryHAKAMI, E; OLOFSSON, S.-O.International FLAC Symposium on Numerical Modeling in Geomechanics. 1999, pp 311-316, isbn 90-5809-074-4Conference Paper

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