Radiation Chemistry inNuclear Engineering 1021
Shoesmith, D.W. 2008. The role of dissolved hydrogen on the corrosion/dissolution of spent nuclear fuel.
NWMO TR-2008-19,
Nuclear
Waste
Management Organization,
Toronto,
Canada.
Shoesmith,
D. W. and King, F. 1999. The effects of gamma radiation of the candidate materials for the fabrica-
tion
of nuclear waste packages.
AECL-11999, Atomic
Energy of Canada Ltd., Pinawa, Canada.
Shoesmith,
D. W., Kolar, M., and King, F. 2003. A mixed-potential model to predict fuel (uranium dioxide)
corrosion
within a failed nuclear waste container. Corrosion 59: 802–816.
Siddall,
T. H. and Dukes, E. K. 1959. Kinetics of HNO
2
catalyzed oxidation of neptunium(V) by aqueous solu-
tions
of nitric acid. J. Am. Chem. Soc. 81: 790–794.
SKB.
2006a. Long-term safety for KBS-3 Reositories at Forsmark and Laxemar – a First Evaluation. Main
Report of the SR-Can project. SKB Technical Report TR-06-09, Swedish Nuclear Fuel and Waste
Management
Co., Stockholm, Sweden.
SKB.
2006b. Fuel and canister process report for the safety assessment SR-Can. SKB Technical Report TR-06-
22,
Swedish Nuclear Fuel and
Waste
Management Co., Stockholm, Sweden.
SKI.
1996. Deep Repository Performance Assessment Project. SKI Report 96:36, Swedish Nuclear Power
Inspectorate,
Stockholm, Sweden.
Smart,
N. R., Rance, A. P., and Werme, L. O. 2008. The effect of radiation on the anaerobic corrosion of steel.
J. Nucl. Mater.
379: 97–104.
Sorel,
C., Montuir, M., Espinoux, D., Lorrain, B., and Baron, P. 2008. Technical feasibility of the DIAMEX
process. In ISEC 2008, International Solvent Extraction Conference, B. A., Moyer (ed.), Tucson, AZ,
pp.
715–720.
Sorieul,
S., Allard, Th., Wang, L. M., Grambin-Lapeyre, C., Lian, J., Calas, G., and Ewing, R. C. 2008.
Radiation
stability of smectite. Environ. Sci. Technol. 42: 8407–8411.
Spahiu,
K., Werme, L., and Eklund, U.-B. 2000. The inuence of near eld hydrogen on actinide solubilities
and
spent fuel leaching. Radiochim. Acta 88: 507–511.
Spahiu
K., Cui, D., and Lundström, M. 2004a. The fate of radiolytic oxidants during spent fuel leaching in the
presence
of dissolved near eld hydrogen. Radiochim. Acta 92: 625–629.
Spahiu
K., Devoy, J., Cui, D., and Lundström, M. 2004b. The reduction of U(VI) by near eld hydrogen in the
presence
of UO
2
(s). Radiochim. Acta 92: 597–601.
Spinks, J. W. T. and Woods, R. J. 1990. An Introduction to Radiation Chemistry, 3rd edn. NewYork: John Wiley
&
Sons.
Stieglitz,
L. and Becker, R. 1985. Chemical and radiolytic solvent degradation in the purex process.
Atomkernenergie-Kerntechnik
46: 76–80.
Sugai,
H. and Munakata, K. 1992. Destruction of emulsions stabilized by precipitates of zirconium and tributyl-
phosphate
degradation products. Nucl. Technol. 99: 235–241.
Sugo,
Y., Sasaki, Y., and Tachimori, S. 2002. Studies on hydrolysis and radiolysis of N,N,N′,N′-tetraoctyl-3-
oxapentane-1,5-diamide.
Radiochim. Acta 90: 161–165.
Sugo,
Y., Izumi,Y., Yoshida,Y., Nishijima, S., Sasaki,Y., Kimura, T., Sekine, T., and Kudo, H., 2007. Inuence
of
diluent on radiolysis of amides in organic solution. Radiat. Phys. Chem. 76: 794–800.
Sunaryo,
G. R., Katsumura, Y., and Ishigure, K. 1995. Radiolysis of water at elevated temperatures—III.
Simulation of radiolytic products at 25 and 250°C under the irradiation with γ-rays and fast neutrons.
Radiat. Phys. Chem.
45:703–14.
Sunder,
S., Shoesmith, D. W., Christensen, H., and Miller, N. H. 1992. Oxidation of UO
2
fuel by the products
of
gamma radiolysis of water. J. Nucl. Mater. 190: 78–86.
Sunder,
S., Boyer, G. D., and Miller, N. H. 1990. XPS studies of UO
2
oxidation by alpha radiolysis of water at
100°C.
J. Nucl. Mater. 175: 163–169.
Suzuki,
H., Shibata, M., Yamagata, J., Hirose, I., and Terakado K. 1992. Characteristic test of buffer material
(I). PNC TN8410 92-057 (in Japanese), Power Reactor and Nuclear Development Fuel Corporation,
Tokai-mura,
Japan.
Suzuki,
T., Abdelouas, A., Grambow, B., Mennecart, T., and Blondiaux, G. 2006. Oxidation and dissolution
rates of UO
2
(s) in carbonate-rich solutions under external alpha irradiation and initially reducing condi-
tions.
Radiochim. Acta 94: 567–573.
Sworski,
T. J., Matthews, R. W., and Mahlman, H. A. 1968. Radiation chemistry of concentrated NaNO
3
solu-
tions:
Dependence of G(HNO
2
) on NaNO
3
concentration. Adv. Chem. Ser. 82: 164–181.
Tahraoui, A. and Morris, J. H. 1995. Decomposition of solvent-extraction media during nuclear reprocessing—
Literature-review.
Sep. Sci. Technol. 30: 2603–2630.
Takagi,
J. and Ichikawa, N. 1999. Modeling technique for BWR primary system corrosion environment. In
Proceedings of the Seminar on Water Chemistry of Nuclear Reactor Systems’99, Tokyo, Japan, pp. 57–61.
Tokyo, Japan: Atomic Energy Society of Japan.