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

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

La conception d'entrepôts spécifiques et leur durabilitéLAURENT, Franck.Revue générale nucléaire. 2006, Num 6, pp 67-72, issn 0335-5004, 6 p.Article

Principles for finding matrices for immobilizing high-level wastesBABAEV, N. S; OCHKIN, A. V; GLAGOLENKO, Yu. V et al.Atomic energy (New York, N.Y.). 2003, Vol 94, Num 5, pp 306-312, issn 1063-4258, 7 p.Article

Concept design of handling system for high level radioactive waste disposalAWANO, Toshihiko; KANNO, Takeshi; ASANO, Hidekazu et al.Ishikawajima-Harima Giho. 2000, Vol 40, Num 4, pp 180-184, issn 0578-7904Article

Effect of dry density on diffusion of some radionuclides in compacted sodium bentoniteSATO, H; ASHIDA, T; KOHARA, Y et al.Journal of Nuclear Science and Technology. 1992, Vol 29, Num 9, pp 873-882, issn 0022-3131Article

Le comportement à long terme des colis de déchetsLIEVEN, Thierry; BLANC, Véronique; GRAS, Jean Marie et al.Revue générale nucléaire. 2006, Num 6, pp 47-52, issn 0335-5004, 6 p.Article

Les conteneurs et leur compatibilité avec le stockageSILVY, Jean-Paul; GAUSSEN, Jean-Louis.Revue générale nucléaire. 2006, Num 6, pp 63-66, issn 0335-5004, 4 p.Article

Repository-heat-driven hydrothermal flow at Yucca Mountain. II: Large-scale in situ heater testsBUSCHECK, T. A; NITAO, J. J; WILDER, D. G et al.Nuclear technology. 1993, Vol 104, Num 3, pp 449-471, issn 0029-5450Article

System analysis dual-purpose repository : new results of temperature calculationsBIURRUN, E; LEMPERT, J. P; ENGELMANN, H.-J et al.Nuclear engineering and design. 1992, Vol 137, Num 1, pp 153-158, issn 0029-5493Article

New analytical method for corrosion studies of radioactive waste glassSATO, S; FURUYA, H; KOJIMA, Y et al.Journal of Nuclear Science and Technology. 1988, Vol 25, Num 10, pp 831-834, issn 0022-3131Article

Development of highly active waste conditioning at SellafieldLARKIN, M. J.Nuclear energy (1978). 1986, Vol 25, Num 6, pp 343-354, issn 0140-4067, part 2Article

The role of the canister in a system for the final disposal of spent fuel or high-level wastePAPP, T.Philosophical transactions of the royal society of London, series A : mathematical and physical sciences. 1986, Vol 319, Num 1545, pp 39-47, issn 0080-4614Article

Solubility of simulated high-level radioactive wastes in CaO-stabilized zirconiaMUROMURA, T; HINATSU, Y.Journal of Nuclear Science and Technology. 1984, Vol 21, Num 10, pp 764-774, issn 0022-3131Article

The leaching behavoir of a glass waste form. I: The characteristics of surface layersMURAKAMI, T; BANBA, T.Nuclear technology. 1984, Vol 67, Num 3, pp 419-428, issn 0029-5450Article

Water migration through compacted bentonite backfills for containment of high-level nuclear wasteWESTSIK, J. H. JR; HODGES, F. N; KUHN, W. L et al.Nuclear and chemical waste management. 1983, Vol 4, Num 4, pp 291-299, issn 0191-815XArticle

CONCEPT OF A CANISTER FOR HIGH-LEVEL RADIOACTIVE WASTEMCCOY HE.1982; NUCL. CHEM. WASTE MANAGE.; ISSN 507563; GBR; DA. 1982; VOL. 3; NO 1; PP. 51-57; BIBL. 17 REF.Article

Salt content impact on the unsaturated property of bentonite-sand buffer backfilling materialsMING ZHANG; HUYUAN ZHANG; LINGYAN JIA et al.Nuclear engineering and design. 2012, Vol 250, pp 35-41, issn 0029-5493, 7 p.Article