Modelling nuclear waste management

Crovisier, J. L., Fritz, B., Grambow, B., Eberhart, J. P. 1985. Dissolution of basaltic glass in seawater experiments and thermodynamic modelling. In Werme, L. O. (ed) Scientific Basis for Nuclear Waste Management IX. Material Research Society Symposium Proceedings, 50, 273-280. 

Modelling near- and far-field processes in nuclear waste management... 

Ellison AJG, Navrotsky A (1990) Thermochemistry and stmcture of model waste glass compositions. In Scientific Basis for Nuclear Waste Management Xlll. Oversby VM, Brown PW (eds). Mater Res Soc SympProc 176 193-207... 

Burkholder, H.C.."Nuclide Migration Models for Faulted Media," in Nuclear Waste Management and Transportation Quarterly Progress Report October Through December 1975, BNWL-1978, Battelle Pacific Northwest Laboratories, Richland, WA,... 

Finite-element modelling of effects of past and future glaciation on the host rock of a used nuclear fuel waste vault. Ontario Hydro Nuclear Waste Management Division Report No. 06819-REP-01200-0020 ROO. Written by Atomic Energy of Canada Limited for Ontario Hydro (now Ontario Power Generation), Toronto,... 

Sheppard, M.L, Sheppard, S.C. and Sanipelli, B. (2002). Recommended Biosphere Model Values for Iodine. Nuclear Waste Management Division Report 06819-REP-01200-10090-R00. Ontario Power Generation, Toronto, Canada. Sheppard, M.L and Thibault, D.H. (1991). J. Environ. Qual 20, 101-114. 

Lichtner, P.C., 1995, Principles and practice of reactive transport modeling. In T. Murakami and R.C. Ewing (eds.), Scientific Basis for Nuclear Waste Management XVIII, vol. 353. Materials Research Society Proceedings, Pittsburgh, PA, pp. 117-130. 

Turner, D.R., T. Griffin, and T.B. Dietrich. 1993. Radionuclide sorption modeling using the MINTEQA2 speciation code. p. 783-789. In C. Interrante and R. Pabalan (ed.) MRS Symp. Proc. Vol. 294. Scientific Basis for Nuclear Waste Management XVI. Mat. Res. Soc., Pittsburgh, PA. 

Alexander, W. R., Gautschi, A. Zuidema, P. 1998. Thorough testing of performance assessment models the necessary integration of in situ experiments, natural analogue studies and laboratory work. Scientific Basis for Nuclear Waste Management, XXI, 1013-1014. 

Wanner, H. 1985. Modelling radionuclide speciation and solubility limits in the near-field of a deep repository. Scientific Basis for Nuclear Waste Management, IX, 509-516. 

Moreton, A. D. 1993. Thermodynamic modelling of the effect of hydroxycarboxylic acids on the solubility of plutonium at high pH. Scientific Basis for Nuclear Waste Management XVI, Materials Research Society Symposium Proceedings, 294, 753-758. 

Waber, H. N. Scholtis, A. 1998. Modelling the chemical evolution of porewater in the Palfris Marl, Wellingberg, Central Switzerland. In McKinley, I. G. McCombie, C. (eds) The Scientific Basis for Nuclear Waste Management XXL Materials Research Society, 789-796. 

Bruno J, Cera E, Grive M, Eklund U-B, Eriksen T. (1999) Experimental determination and chemical modelling of radiolytic processes at the spent fuel/water interface. Swedish Nuclear Euel and Waste Management Co, TR-99-26. 

Rhen I., Gustafson G., Stanfors R., and Wikberg P. (1997) Aspo HRL—Geoscientific Evaluation 1997/5. Models Based on Site Characterization 1986-1995. Technical Report 97-06, Swedish Nuclear Fuel and Waste Management Company (SKB), 428p. 

In the field of radioactive waste management, the hazardous material consists to a large extent of actinides and fission and activation products from nuclear reactors (such is the case of the fission product Se). The scientific literature on thermodynamic data, mainly on equilibrium constants and redox potentials in aqueous solution, has been contradictory in a number of cases. A critical and comprehensive review of the available literature is necessary in order to establish a reliable thermochemical database that fulfils the requirements of a proper modelling of the behaviour of the actinide and fission and activation products in the environment. 

The need to make available a comprehensive, internationally recognised and quality-assured chemical thermodynamic database that meets the modeling requirements for the safety assessment of radioactive waste disposal systems prompted the Radioactive Waste Management Committee (RWMC) of the OECD Nuclear Energy Agency (NEA) to launch in 1984 the Thermochemical Database Project (NEA-TDB) and to foster its continuation as a semi-autonomous project known as NEA-TDB Phase 11 in 1998. 

Hung C.Y. (1986), An Optimum Groundwater Transport Model for Application to the Assessment of Health Effects Due to Land Disposal of Radioactive Wastes. Proceedings of Nuclear and Chemical Wastes Management, Vol. 6, pp. 41-50. 

Fredriksson, A., Staub, I., Janson, T. 2003. Aspo Pillar Stability Experiment. Design of heaters and preliminary results from coupled 2D thermo-mechanical modelling. SKB, IPR-03-03. Swedish Nuclear Fuel and Waste Management Company, Stockholm. 

Cheng, H., and Cvetkovic, V., (in prep). Modelling of sorbing tracer breakthrough for Task 6A, 6B and 6B2, Swedish Nuclear Fuel and Waste Management Co. (SKB). 

Rinne M, Shen B, Lee H-S, 2003. Aspo pillar stability experiment. Part I Modelling of fracture stability by FRACOD. Part II Modelling Fracture Initiation and Acoustic Emission. Part III Reconstruction of Stress Field Using an Inverse Technique. International Progress Report, IPR-03-05. Swedish Nuclear Fuel and Waste Management Company, Stockholm, 2003. 

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