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Long-term product consistency test of simulated 90-19/Nd HLW glassGAN, X. Y; ZHANG, Z. T; YUAN, W. Y et al.Journal of nuclear materials. 2011, Vol 408, Num 1, pp 102-109, issn 0022-3115, 8 p.Article

Release of neptunium from neptunium-doped borosilicate waste glassNAKAYAMA, S; BANBA, T.Journal of Nuclear Science and Technology. 1989, Vol 26, Num 6, pp 607-615, issn 0022-3131, 9 p.Article

Characterization of borosilicate glass-containing Savannah River plant radioactive waste: MCC-1 tests and durability in geologic repository groundwatersBIBLER, N. E.A.C.S. symposium series. 1983, Num 246, pp 359-372, issn 0097-6156Article

The 1000-year prediction : A state-of-the-art review on the resarch activity for the structural integrity of geological disposal packages of high-level nuclear wasteAKASHI, M.Ishikawajima-Harima Giho. 1996, Vol 36, Num 4, pp 280-291, issn 0578-7904Article

Phénoménologie de la radiolyse de sels : application au stockage des déchets nucléaires de haute activité = Radiolysis salt phenomenology : application to storage of high level radioactive wasteAKRAM, Najib; TREMILLON, Bernard.1993, 231 p.Thesis

Reaction between simulated high-level radioactive waste and Y2O3-stabilized zirconia in airMUROMURA, T; HINATSU, Y.Journal of nuclear materials. 1986, Vol 137, Num 3, pp 227-235, issn 0022-3115Article

Interaction between borosilicate melt and InconelSENGUPTA, Pranesh; MITTRA, J; KALE, G. B et al.Journal of nuclear materials. 2006, Vol 350, Num 1, pp 66-73, issn 0022-3115, 8 p.Article

High level liquid waste vitrification technologyKITAMURA, M; SHIRATO, K; SAKAI, A et al.Ishikawajima-Harima Giho. 1997, Vol 37, Num 4, pp 258-264, issn 0578-7904Article

Volatilization of cesium from nuclear waste glass in a canisterKAMIZONO, H; KIKKAWA, S; TASHIRO, S et al.Nuclear technology. 1986, Vol 72, Num 1, pp 84-88, issn 0029-5450Article

Segregation of the elements of the platinum group in a simulated high-level waste glassMITAMURA, H; MURAKAMI, T; BANBA, T et al.Nuclear and chemical waste management. 1983, Vol 4, Num 3, pp 245-251, issn 0191-815XArticle

Study of an optimization approach for a disposal tunnel layout, taking into account the geological environment with spatially heterogeneous characteristicsSUYAMA, Yasuhiro; TOIDA, Masaru; YANAGIZAWA, Koichi et al.Nuclear engineering and design. 2009, Vol 239, Num 9, pp 1693-1698, issn 0029-5493, 6 p.Conference Paper

La caractérisation, un apport à la connaissance du colis de déchetsHABLOT, Isabelle; SAUVAGE, Laurent.Revue générale nucléaire. 2006, Num 6, pp 22-29, issn 0335-5004, 8 p.Article

Axe de recherche 3 : Les procédés de conditionnement et d'entreposage de longue durée = The main thrust of research 3 : the conditioning and long-lived storageRevue générale nucléaire. 2005, Num 4, pp 42-44, issn 0335-5004, 3 p.Conference Paper

Operation of the Pamela high-level waste vitrification facilityWIESE, H; DEMONIE, M.Nuclear engineering and design. 1992, Vol 137, Num 1, pp 147-151, issn 0029-5493Article

Procédé de rétraction et résistance à la compression lors de la méthode hydrothermale de pressage à chaud des déchets fortement radioactifsYAMASAKI, N; NISHIOKA, M; YANAGISAWA, K et al.Yogyo kyokaishi. 1985, Vol 93, Num 3, pp 151-153, issn 0009-0255Article

Recherches sur la gestion des déchets radioactifs à haute activité et à vie longue : axe 3 - Procédés de conditionnement et d'entreposage de longue durée = Research on high activity long-lived radwaste management : axis 3 - Conditioning and long duration storageCOURTOIS, Charles.Revue générale nucléaire. 2006, Num 6, issn 0335-5004, [56 p.]Serial Issue

Les potentialités des entrepôts industriels vis-à-vis de la longue duréeBRETON, Elsa; DEVEZEAUX DE LAVERGNE, Jean Guy; BARBRAULT, Patrick et al.Revue générale nucléaire. 2006, Num 6, pp 53-62, issn 0335-5004, 10 p.Article

La recherche pour la gestion des déchets à haute activité et à vie longue = The research for the management of high-level, long-lived wastesOUZOUNIAN, G; BUFFEREAU, M; JACQ, F et al.Revue générale nucléaire. 1997, Num 5, issn 0335-5004, p. 45Article

Filtration characteristics of slurry formed by denitration of simulated high-level liquid wasteKONDO, Y.Journal of radioanalytical and nuclear chemistry. 1995, Vol 191, Num 1, pp 115-128, issn 0236-5731Article

Probability networks for handling uncertainty in the performance assessment of high-level nuclear waste repositoriesSHARIF HEGER, A; HILL, J. R.Reliability engineering & systems safety. 1993, Vol 41, Num 1, pp 13-20, issn 0951-8320Article

Volatility of simulated high-level nuclear waste glass by thermogravimetric analysisHARBOUR, J. R.Journal of the American Ceramic Society. 1992, Vol 75, Num 3, pp 507-513, issn 0002-7820Article

Crystalline phases in a devitrified simulated high-level waste glass containing the elements of the platinum groupMITAMURA, H; MURAKAMI, T; BANBA, T et al.Journal of nuclear materials. 1985, Vol 136, Num 1, pp 104-116, issn 0022-3115Article

Powder technological vitrification of medium and high level waste by in-can hot pressingONDRACEK, G; TOSCANO, E. H.Kernforschungszentrum Karlsruhe. 1984, Num 3814, issn 0303-4003, 11 p.Serial Issue

Effects of Hanford high-level waste components on the solubility and sorption of cobalt, strontium, neptunium, plutonium, and americiumDELEGARD, C. H; BARNEY, G. S; GALLAGHER, S. A et al.A.C.S. symposium series. 1983, Num 246, pp 95-112, issn 0097-6156Article

Thermal shock resistance of a simulated high-level waste glassKAMIZONO, H; SENOO, M.Nuclear and chemical waste management. 1983, Vol 4, Num 4, pp 329-333, issn 0191-815XArticle

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