Print Friendly and PDF

Radioactive Waste Management Data Sources

Jason -

The references on this page will be useful for those who are using GoldSim for radioactive waste management applications. Although this list is by no means exhaustive, it provides an excellent collection of data sources. If you have a reference that you think might be useful, please add it here or contact .

Key to information content

1 = Partition coefficients for radionuclides in bentonite
2 = Partition coefficients for radionuclides in cement
3 = Partition coefficients for radionuclides in fractured rock & fracture minerals
4 = Partition coefficients for radionuclides in clays
5 = Diffusivities for radionuclides in bentonite
6 = Diffusivities for radionuclides in cement
7 = Diffusivities for radionuclides in fractured rock
8 = Diffusivities for radionuclides in clays
9 = Porosities in bentonite
10 = Porosities in cement
11 = Porosities in fractured rock
12 = Porosities in clays
13 = Solubilities & speciations of radionuclides
14 = Permeabilities in compacted bentonite
15 = Permeabilities in cement
16 = Permeabilities in fractured rock
17 = Permeabilities in clays
18 = Other properties of solid media, e.g. surface area, cation exchange capacity
19 = Thermal conductivities of solid media
20 = Partition coefficients for radionuclides in biosphere objects
21 = Transfer functions for radionuclide uptake in biosphere objects
22 = Dose conversion factors for biosphere objects
23 = Radionuclide decay rates and decay chains
24 = General performance assessment
 

European Commission Research Reports

  • EUR 17643EN. 1998 The performance of cementitious barriers in repositories. 309pp. Office for Official Publications of the EC, Luxembourg (Harris, A.W., Atkinson, A., Balek, V., Brodersen, K., Cole, G.B., Haworth, A., Malek, Z., Nickerson, A.K., Nilson, K. and Smith, A.C.) {2, 6, 10, 15}
  • EUR 19780EN. 2001 Barrier performance of cements and concretes in nuclear waste repositories. European Commission, Office of Publications, Luxembourg. (KINA) {2, 6, 10, 15}


 

Andra (France) Reports

  • Report ‘Dossier 2005 Argile’ 2005 Tome: Phenomenological evolution of a geological repository. Andra, Paris. {24}
  • Report ‘Dossier 2005 Argile’ 2005 Tome: Safety evaluation of a geological repository. Andra, Paris. {24}
  • Report ‘Dossier 2005 Argile’ 2005 Synthesis: Evaluation of the feasibility of a geological repository in an argillaceous formation. Meuse/Haute Marne site. Andra, Paris. {24}
  • Report ‘Dossier 2005 Argile’ 2005 Tome: Architecture and management of a geological repository. Andra, Paris. {24}
  • Report ‘Dossier 2005’ 2005 Andra research on the geological disposal of high-level long-lived radioactive waste. Results and perspectives. Andra, Paris. {24}
  • Report ‘Dossier 2005 Argile’ 2005 Tome: Évaluation de sûreté du stockage géologique. Andra, Paris. {24}
  • Report ‘Dossier 2005 Argile’ 2005 Tome: Architecture et gestion du stockage géologique. Andra, Paris. {24}
  • Report ‘Dossier 2005 Argile’ 2005 Tome: Évolution phénoménologique du stockage géologique. Andra, Paris. {24}
  • Report ‘Dossier 2005 Argile’ 2005 Le milieu géologique: le site de Meuse/Haute Marne. Andra, France. {24}
  • Report ‘Dossier 2005 Granite’ 2005 Tome: Évolution phénoménologique du stockage géologique. Andra, Paris. {24}
  • Report ‘Dossier 2005 Granite’ 2005 Tome: Architecture et gestion du stockage géologique. Andra, Paris. {24}
  • Report ‘Dossier 2005 Granite’ 2005 Tome: Analyse de sûreté du stockage géologique. Andra, Paris. {24}
  • Report ‘Dossier 2005’ 2005 Les recherches de l’Andra sur le stockage géologique des déchets radioactifs à haute activité et à vie longue. Andra, Paris. {24}


 

AECL, NWMO, OPG (Canada) reports

  • Report AECL-10719 1994 The disposal of Canada’s nuclear fuel waste: the geosphere model for postclosure assessment. AECL Whiteshell, Pinawa (C C Davison et al) {24}


 

Enresa (Spain) Reports

  • Enresa Pub. Tec. Num 06-97 1997 Evaluacion del Comportamiento y de la Seguridad de un Almacenamiento Geologico Profundo en Granito. {3, 7, 13, 24}
  • Enresa Pub. Tec. Num 02-98 1997 Performance Assessment of a Deep Geological Repository in Granite {3, 7, 13, 24}
  • Enresa Pub. Tec. Num 03-99 1999 Evaluacion del Comportamiento y de la Seguridad de un Almacenamiento Profundo en Arcilla {4, 8, 13, 24}


 

JNC/JAEA (Japan) Reports

  • JNC H12 2000 Project to Establish the Scientific and Technical Basis for HLW Disposal in Japan. Second Progress Report on Research and Development for the Geological Disposal of HLW in Japan. Japan Nuclear Cycle Development Institute, Tokyo {13}


 

Nagra & PSI (Switzerland) Reports

  • Nagra Technical Report 84-40 1985 Radionuclide Sorption Database for Swiss Safety Assessment. Nationale Genossenschaft für Die Lagerung radioaktiver Abfälle, Wettingen, Switzerland (McKinley, I.G. and Hadermann, J.) {3}
  • Nagra Technical Report NTB 85-21 1985 Radionuclide sorption on concrete. Nagra, Wettingen, Switzerland (Allard, B.) {2}
  • Nagra Technical Report 93-22 1994 Kristallin-1. Safety Assessment Report. Nationale Genossenschaft für Die Lagerung radioaktiver Abfälle, Wettingen, Switzerland {3, 7, 13, 16, 18, 19, 24}
  • Nagra Technical Report 94-08 1995 Kristallin-1 Estimates of Solubility limits for Safety Relevant Radionuclides. (Berner, U.) {13}
  • Nagra Technical Report NTB 02-02 2002 Project Opalinuston. Konzept für die Anlage und den Betrieb eines geologische Tiefenlagers. Entsorgungsnachweis für abgebrannte Brennelemente, verglaste hochaktive sowie langlebige mittelaktive Abfälle {24}
  • Nagra Technical Report NTB 02-03 2002 Project Opalinuston. Synthese der geowissenschaftlichen Untersuchungsergebnisse. Entsorgungsnachweis für abgebrannte Brennelemente, verglaste hochaktive sowie langlebige mittelaktive Abfälle {24}
  • Nagra Technical Report NTB 02-05 2002 Project Opalinus Clay. Safety Report. Demonstration of disposal feasibility for spent fuel, vitrified high-level waste and long-lived intermediate-level waste (Entsorgungsnachweis) {24}
  • Nagra 2003 Projekt Opalinuston: Entsorgungsnachweis für abgebrannte Brennelemente, verglaste hochaktive sowie langlebige mittelaktive Abfälle. Zusammenfassender Überblick {24}
  • PSI Bericht Nr. 95-06 1995 Sorption Databases for the Cementitious Near-Field of a L/ILW Repository for Performance Assessment. Paul Scherrer Institut, Villigen, Switzerland (Bradbury, M.H. and Sarott, F-A.) {2}
  • PSI Bericht Nr. 98-01 1997 Cementitious Near-Field Sorption Databases for Performance Assessment of a L/ILW Repository in a Palfris Marl Host Rock. CEM-94: Update 1, June 1997. Paul Scherrer Institut, Villigen, Switzerland (Bradbury, M.H. and Van Loon, L.R.) {2}
  • PSI-Bericht Nr. 99-05 1999 Diffusion and sorption on hardened cement pastes – experiments and modelling results. Waste Management Laboratory, Paul Scherrer Institute, Würenlingen, Switzerland. 186pp (Jakob, A., Sarott, F.-A. and Spieler, P.) {2}
  • PSI Bericht Nr. 99-10 1999 Concentration Limits in the Cement Based Swiss Repository for Long-lived, Intermediate-level Radioactive Wastes (LMA). Waste Management laboratory, Paul Scherrer Institute, Villigen, Switzerland (Berner, U.) {13}
  • PSI-Bericht Nr. 02-26 2002 Project Opalinus Clay: Radionuclide concentration limits in the cementitious near-field of an ILW repository. Nuclear Energy and safety Research Department, Laboratory for Waste Management, Paul Scherrer Institute, Willigen, Switzerland (Berner, U.) {13}




 

Nirex, NDA, AEAT & Serco (UK) Reports

  • Nirex Science Report S/95/011 1994 Nirex Safety Assessment Research Programme Science Report. Nirex Near Field Research: Report on Current Status in 1994. UK Nirex, Harwell, UK. {2, 6, 10, 13}
  • Nirex Science Report S/97/012 1997 An Assessment of the Post-closure Performance of a Deep Waste Repository at Sellafield. Overview. UK Nirex, Harwell (S Norris et al) {24}
  • Nirex Science Report S/97/012 1997 An Assessment of the Post-closure Performance of a Deep Waste Repository at Sellafield. Volume 1: Hydrogeological Model Development – Conceptual Basis and Data. UK Nirex, Harwell {24}
  • Nirex Science Report S/97/012 1997 An Assessment of the Post-closure Performance of a Deep Waste Repository at Sellafield. Volume 2: Hydrogeological Model Development – Effective Parameters and Calibration. UK Nirex, Harwell (C P Jackson & S P Watson) {11, 16, 24}
  • Nirex Science Report S/97/012 1997 An Assessment of the Post-closure Performance of a Deep Waste Repository at Sellafield. Volume 3: The Groundwater Pathway. UK Nirex, Harwell {2, 3, 7, 10, 16, 24}
  • Nirex Science Report S/97/012 1997 An Assessment of the Post-closure Performance of a Deep Waste Repository at Sellafield. Volume 4: The Gas Pathway. UK Nirex, Harwell (A J Baker et al) {24}
  • Nirex Science Report S/97/014 1997 Nirex Reference Vault Backfill: Current Status 1994. UK Nirex, Harwell. {2, 6}
  • Nirex Science Report S/98/008 1998 Sorption of radionuclides by cement minerals. Proc. of the Royal Society of Chemistry/Nirex Symposium: The Chemistry of Deep Disposal of Radioactive Waste. UK Nirex, Harwell (Baker, S., Heath, T.G. and McCrohon, R.) {2}
  • Nirex Safety Series Report NSS/R122 1988 The solubility and sorption of protactinium in the near-field and far-field environments of a radioactive waste repository. UK Nirex Ltd, Harwell (Berry, J.A., Hobley, J. and Lane, S.A.) {2, 3, 13}
  • Nirex Safety Series Report NSS/R162 1988 Safety Studies Nirex Radioactive Waste Disposal Review of Sorption Data applicable to the Geological Environments of Interest for the Deep Disposal of ILW and LLW in the UK (JJW Higgo) {3, 4}
  • Nirex Safety Studies Report NSS/R186 1990 The solubility and sorption of nickel and niobium under high pH conditions. UK Nirex, Harwell (Pilkington, M.J. and Stone, N.S.) {2, 13}
  • Nirex Safety Studies Report NSS/R203 1999 The effect of organic degradation products on the sorption of actinides on cement matrices. UK Nirex, Harwell. (M Brownsword et al) {2}
  • Nirex Safety Studies Report NSS/R216 1990 Diffusion under water-saturated conditions in PFA/OPC-based structural concrete. UK Nirex, Harwell. (A W Harris & A K Nickerson) {6}
  • Nirex Safety Studies Report NSS/R309 1995 The mass-transport properties of cementitious materials for radioactive waste repository construction. UK Nirex, Harwell (Harris, A.W. and Nickerson, A.K.) {6, 10, 15}
  • Nirex Safety Series Report NSS/R312 2000 Sorption of Radionuclides onto Specific Mineral Phases Present in Repository Cements. AEAT Report D&R-0395. UK Nirex Ltd, Harwell (Aggarwal S., Angus M.J. and Ketchen J.) {2}
  • Nirex Safety Studies Report NSS/R357 1996 Further near-field solubility studies. UK Nirex, Harwell. (G M N Baston et al) {13}
  • Nirex Safety Studies Report NSS/R389 1997 The performance of cementitious barriers in repositories. UK Nirex, Harwell. (A W Harris et al) [2, 6, 10, 15}
  • Nirex Report N/031 2001 Generic post-closure performance assessment. UK Nirex, Harwell. (L E F Bailey et al) {24}
  • Nirex Report N/052 2003 Current status of far-field sorption modelling studies. UK Nirex, Harwell. (K A Bond et al) {3}
  • AERE-R11881 1985 Review of Sorption Data for Site Assessment. U.K. Atomic Energy Authority, Harwell (Bradbury, M.H. and Jefferies, N.L.) {3}
  • AERE-M3452 1985 Near field sorption data for cesium and strontium. U.K. Atomic Energy Authority, Harwell (Ewart, F.T., Terry, S. and Williams, S.J.) {3}
  • AEAT/R/ENV/0205 2000 An experimental study of actinide sorption onto calcite, aluminium oxide and hematite. Report for UK Nirex Ltd. (J A Berry et al) {3}
  • AEAT/R/ENV/0213 2001 An overview of NSARP investigations into non-linear sorption. Report produced for UK Nirex Ltd. (K A Bond et al, eds) {2, 3}
  • AEAT/R/ENV/0214 2001 Interpretation and modelling of Radioelement Sorption Data Obtained under Alkaline Conditions. Report produced for UK Nirex Ltd. (Bond, K.A., Linklater, C.M., Tweed, C.J.) {2}
  • AEAT/R/ENV/0215 2001 Sorption of radionuclides onto rock samples from the Sellafield area: database of distribution ratios. Report for UK Nirex Ltd. (K A Bond & C M Linklater) {3}
  • AEAT/R/ENV/0229 2000 Development of a near-field sorption model for a cementitious repository. Report for UK Nirex Ltd. (T G Heath et al) {2}
  • AEAT/R/ENV/0233 2000 The aqueous solubility behaviour of selenium, technetium and tin. Report produced for UK Nirex Ltd. (S Baker et al)
  • AEAT/R/ENV/0531 2002 Measurements of the solubility of chromium and the solubility and sorption of molybdenum under cementitious repository conditions. Report for UK Nirex Ltd. (S Baker & S J Williams) {2, 13}
  • Serco SA/ENV-0447 2003 An overview of research on diffusion in the geosphere undertaken within the Nirex Safety Assessment Research Programme. Report produced for UK Nirex Ltd. (N L Jefferies & S W Swanton) {7, 8, 11, 12}
  • Serco SA/ENV-0599 2004 Database of rock matrix diffusion parameters – issue 3. Report produced for UK Nirex Ltd. (S W Swanton et al) {7, 11, 16}
  • Serco SA/ENV-0646 2006 The diffusion of radionuclides through waste encapsulation grouts. Report produced for UK Nirex Ltd. (A V Chambers et al) {6}
  • Serco SA/ENV/0920 2007 Formal structured data elicitation of uranium solubility in the near field. Report for UK Nirex Ltd. (D Swan & C P Jackson) {13}
  • Serco SA/ENV-1002 2008 Strategy for the treatment of uncertainty in solubility, sorption and diffusion data for a UK HLW repository. Report to NDA (S W Swanton et al) {3, 7, 13}


 

Posiva (Finland) Reports

  • YJT Report YJT-84-04 1984 Sorption of Sr, Cs, Ni, I and C in concrete. Voimayhtiöiden Ydinjätetoimikunta, Helsinki, Finland (Hietanen, R., Kämäräinen, E-L. and Alaluusua, M.) {2}
  • Posiva 96-17 1996 Interim report on safety assessment of spent fuel disposal – TILA-96 (T Vieno & H Nordman) {1, 3, 5, 7, 9, 11, 13, 16, 22, 23, 24}
  • Posiva 99-07 1999 Safety assessment of spent fuel disposal in Hästholmen, Kivetty, Olkiluoto and Romuvaara – TILA-99 (T Vieno & H Nordman) {1, 5, 9, 7, 11, 13, 16, 18, 23, 22}
  • Posiva 2004-05 2004 Localisation of the SR97 process report for Posiva’s spent fuel repository at Olkiluoto (Ed: K Rasilainen) {19}
  • Posiva 2007-07 2007 Safety Assessment for KBS-3H Spent Nuclear Fuel Repository at Olkiluoto: Radionuclide Transport Report (P Smith et al) {1, 3, 7, 18, 11, 13}
  • Posiva 2007-09 2007 Safety Assessment for KBS-3H Spent Nuclear Fuel Repository at Olkiluoto: Process Report, Posiva Oy, Helsinki (P Gribi et al) {11, 16, 19}
  • Posiva 2008-06 2008 Radionuclide release and transport RNT-2008 (M Nykyri et al) {3, 5, 9, 7, 11, 13, 16, 23, 22}
  • Posiva Working Report 2007-103 2008 Assessment of the concentration limits for radionuclides for Posiva (M Grivé, V Montoya & L Duro) {13}
  • Posiva Working Report 2007-107 2008 Models used in the SFR1 SAR-08 and KBS-3H safety assessments for calculation of C-14 doses (R Avia & G Pröhl) {20, 21, 22}
  • Posiva Working Report 2007-109 2008 Biosphere analysis for selected cases in TILA-99 and in KBS-3H safety evaluation 2007 (R Broed et al) {22}
  • Posiva Working Report 2008-52 2008 Groundwater flow and transport simulations in support of RNT-2008 analysis (J Löfman & A Poteri) {11,16}
  • Posiva Working Report 2008-62 Sorption of cesium on Olkiluoto mica gneiss and granodiorite in saline groundwater; retardation of cesium transport in rock fracture columns (J Kyllönen et al) {3, 18}
  • Posiva Working Report 2009-33 2009 Chemical and geotechnical analyses of soil samples from Olkiluoto for studies on sorption in soils (M Lusa et al) {18}


 

SKB (Sweden) Reports

  • SKB TR 83-13 1983 Sorption and diffusion studies of Cs and I in concrete. (Andersson, K., Torstenfelt, B. and Allard, B.) {2}
  • SKB TR-99-06 1999 SR 97 – Post-closure safety: Deep repository for spent nuclear fuel Main Report Summary {24}
  • SKB TR-99-06 1999 SR 97 – Post-closure safety: Deep repository for spent nuclear fuel Main Report Volume I {19, 16, 23, 24}
  • SKB TR-99-06 1999 SR 97 – Post-closure safety: Deep repository for spent nuclear fuel Main Report Volume II {1, 3, 5, 7, 9, 11, 13, 22, 24}
  • SKB TR-99-07 1999 SR 97 - Processes in the repository evolution: Background report to SR97 {24}
  • SKB TR-99-08 1999 SR 97 - Waste, repository design and sites: Background report to SR 97 {19, 16}
  • SKB TR-99-09 1999 SR 97 - Data and data uncertainties: Compilation of data and data uncertainties for radionuclide transport calculations (J Andersson et al) {1, 3, 5, 7, 9, 11, 13, 22}
  • SKB TR-99-20 1999 SR 97 – Identification of structuring of process (K Pers et al) {24}
  • SKB TR-99-23 1999 SR 97 - Radionuclide transport calculations (M Lindgren et al) {3, 7, 11, 1, 9, 13, 22, 23}
  • SKB TR-03-07 2003 The Buffer and Backfill Handbook Part 3: Models for calculation of processes and behaviour (R Pusch) {5, 14, 19}
  • SKB TR-04-18 2004 SR-Can - Data and uncertainty assessment: Migration parameters for the bentonite buffer in the KBS-3 concept (M Ochs et al) {1, 5, 9}
  • SKB TR-06-09 2006 Long-term safety for KBS-3 repositories at Forsmark and Laxemar – a first evaluation. Main report of the SR-Can project {24}
  • SKB TR-06-17 2006 Update of thermodynamic database for radionuclides to assist solubility limits calculation for performance assessment (L Duro et al) {13}
  • SKB TR-06-25 2006 Data report for the safety assessment SR-Can {1, 3, 5, 9, 13, 14, 16, 19}
  • SKB TR-06-32 2006 Determination and assessment of the concentration limits to be used in SR-Can (L Duro et al) {13}
  • SKB TR-08-09 2008 Element composition of biota, water and sediment in the Forsmark area, Baltic Sea Concentrations, bioconcentration factors and partitioning coefficients (Kd) of 48 elements (L Kumblad et al) {20, 21}
  • SKB R-97-13 1997 Compilation of radionuclide sorption coefficients for performance assessment (P Carbol et al) {3}
  • SKB R-97-15 1997 Review of a report on diffusion and sorption properties of radionuclides in compacted bentonite (M Ochs) {1, 5}
  • SKB R-98-43 1998 Project SAFE: Update of the SFR-1 safety assessment, Phase 1 (J Andersson et al) {24}
  • SKB R-98-44 2001 Project SAFE: Update of the SFR-1 safety assessment, Phase 1 Appendices {24}
  • SKB R-99-13 1999 Compilation of data for the analysis of radionuclide migration from SFL 3-5 (K Skagius et al) {2, 6, 7, 11, 13, 16, 18}
  • SKB R-01-08 2001 Project SAFE: Modelling of long-term concrete degradation processes in the Swedish SFR repository (L Hoglund et al) {6, 9, 10}
  • SKB R-01-13 2001 Project SAFE: Scenario and system analysis {24}
  • SKB R-01-14 2001 Project SAFE: Compilation of data for radionuclide transport analysis {13, 1, 2, 3, 5, 6, 9, 10, 11, 16, 18}
  • SKB R-01-18 2001 Project SAFE: Radionuclide release and dose from the SFR repository (M Lindgren et al) {24}
  • SKB R-02-28 2002 Nuclide documentation: Element specific parameter values used in the biospheric models of the safety assessments SR97 and SAFE(S Karlsson et al) {20, 21, 22}
  • SKB R-06-111 2006 SR-Can - Data and uncertainty assessment: Matrix diffusivity and porosity in situ (J Liu et al) {7, 11}
  • SKB R-06-75 2006 Data and uncertainty assessment for radionuclide Kd partitioning coefficients in granitic rock for use in SR-Can calculations (J Crawford) {3}
  • SKB R-08-130 2008 Safety analysis, SFR1: Long-term Safety {1, 2, 3, 7, 11, 18, 23}
  • SKB P-07-139 2008 Forsmark site investigation - Laboratory measurements within the site investigation programme for the transport properties of the rock: Final Report (E Selnert et al) {3, 18}




 

SKI/SSM (Sweden) Reports

  • SKI 96:2 1996 Site-94 - Chemical and Physical Transport Parameters for SITE-94. Swedish Nuclear Power Inspectorate, Stockholm (K Andersson) {3, 7, 11, 13, 16}
  • SKI 96:36 1996 SKI Site-94 - Deep Repository Performance Assessment Project: Volume I 16, 24}
  • SKI 96:36 1996 SKI Site-94 - Deep Repository Performance Assessment Project: Volume II {1, 3, 5, 7, 11, 13, 16, 18, 22, 23, 24}
  • SKI 97:5 1997 SKI Site-94 - Deep Repository Performance Assessment: Project Summary {24}
  • SKI 99:9 1999 Review of the Properties and Uses of Bentonite as a Buffer and Backfill Material (D Savage et al) {1, 5, 9}
  • SKI 00:49 2000 Evolution of Near Field Physico-Chemical Characteristics of the SFR Repository (D Savage et al) {2}
  • SKI 02:35 2002 Encyclopaedia of Features, Events and Processes (FEPs) for the Swedish SFR and Spent Fuel Repositories (B Miller et al) {24}
  • SKI 02:62 2002 Exploration of Important Issues for the Safety of SFR 1 using Performance Assessment Calculations (P Maul et al) {1, 2, 3, 5, 6, 7, 9, 10, 11, 13, 18, 20, 22, 24}


 

US Reports

  • Report ORNL-6783/R1 1997 Transport related properties of radionuclides in waste and concrete used in the performance assessment of SWSA 6 disposal facilities, Volume 1 (Appendix C of: Performance assessment for continuing and future operations at SWSA 6). Oak Ridge National Laboratory (Godbee, H.W., Icenhour, A.S., Loghry, S.L., Tharp.) {2, 6, 10, 15}
  • Report PNNL-11800 1998 Composite analysis for low-level waste disposal in the 200 Area Plateau of the Hanford site. Pacific Northwest National Laboratory(Kincaid, C.T., Bergeron, M.P., Cole, C.R., Freshley, M.D., Hassig, N.L., Johnson, V.G., Kaplan, D.I., Serne, R.J., Streile, G.P., Strenge, D.L., Thorne, P.D., Vail, L.W., Whyatt, G.A. and Wurstner, S.K.)
  • Report NUREG/CR-4269 1991 Models of Transport Processes in Concrete. National Institute of Standards and Technology, Gaithersburg, MD, U.S.A. for the U.S. Nuclear Regulatory Commission, Washington, D.C. (Pommersheim, J.M. and Clifton, J.R.) {6, 15}
  • Report NUREG/CR-6070 1993 Modeling Approaches for Concrete Barriers Used in Low-level Waste Disposal. US Nuclear Regulatory Commission, Washington, D.C. (Seitz, R.R. and Walton, J.C.)
  • Report NUREG/CR-6377 1996 Performance Assessment of Low-level Radioactive Waste Disposal Facilities: Effects on Radionuclide Concentrations by Cement/Groundwater Interactions. US Nuclear Regulatory Commission, Washington, D.C. (Krupka, K.M. and Serne, R.J.) {13}
  • OCRWM Report ALN-WIS-MD-000010 2000 Summary of dissolved concentration limits. Analysis model report for TSPA, rev00. Yucca Mountain Project Office. US Department of Energy, Office of Civilian Radioactive Waste Management {13}
  • OCRWM Report ANL-EBS-MD-000034 2000 EBS radionuclide transport model, rev00. Yucca Mountain Project Office. US Department of Energy, Office of Civilian Radioactive Waste Management {3, 16}
  • OCRWM Report ANL-EBS-MD-000017 2000 Pure phase solubility limits - LANL, rev00. Yucca Mountain Project Office. US Department of Energy, Office of Civilian Radioactive Waste Management {13}
  • OCRWM Report TDR-NBS-HS-000001 2000 Unsaturated zone flow and transport model process model report, rev00. Yucca Mountain Project Office. US Department of Energy, Office of Civilian Radioactive Waste Management {3, 7, 11, 16, 18}
  • OCRWM Report ANL-NBS-HS-000019 2001 Unsaturated zone and saturated zone transport properties, rev00. Yucca Mountain Project Office. US Department of Energy, Office of Civilian Radioactive Waste Management {3, 7, 16}
  • OCRWM Report ANL-WIS-MD-000010 2003 Dissolved concentration limits of radioactive elements, rev02. Yucca Mountain Project Office. US Department of Energy, Office of Civilian Radioactive Waste Management {13}
  • OCRWM Report MDL-NBS-HS-000011 2003 Site-scale saturated zone flow model, rev01. Yucca Mountain Project Office. US Department of Energy, Office of Civilian Radioactive Waste Management {16, 19}
  • OCRWM Report ANL-WIS-MD-000010 2003 Dissolved concentration limits of radioactive elements, rev02. Yucca Mountain Project Office. US Department of Energy, Office of Civilian Radioactive Waste Management {13}
  • OCRWM Report MDL-NBS-HS-000001 2003 Drift-scale coupled processes (DST and THC seepage) models, rev02. Yucca Mountain Project Office. US Department of Energy, Office of Civilian Radioactive Waste Management {11, 16, 18, 19}
  • OCRWM Report ANL-EBS-MD-000049 2004 Multiscale thermohydrologic model, rev01. Yucca Mountain Project Office. US Department of Energy, Office of Civilian Radioactive Waste Management {16, 19}
  • OCRWM Report MDL-NBS-HS-000010 2005 Site-scale saturated zone transport, rev02. Yucca Mountain Project Office. US Department of Energy, Office of Civilian Radioactive Waste Management {3, 7, 11, 16, 18}
  • OCRWM Report MOD-06-001 2007 Geochemical modelling of solubility and speciation of uranium, neptunium and plutonium, rev00. Yucca Mountain Project Office. US Department of Energy, Office of Civilian Radioactive Waste Management {13}


 

Published papers

  • Albinsson Y., Andersson K., Börjesson S. and Allard B. 1996 Diffusion of radionuclides in concrete and concrete-bentonite systems. J. Contaminant Hydrol., 21, 189-200 {6}
  • Atkinson A. and Nickerson A.K. 1988 Diffusion and sorption of cesium, strontium, and iodine in water-saturated cement. Nucl. Technol., 81, 100-113 {2, 6}
  • Atkinson, A. and Nickerson, A.K. 1984 The diffusion of ions through water-saturated cements. J. Materials Science, 19, 3068-3078 {6}
  • Brown, P.L., Haworth, A., McCrohon, R., Sharland, S.M. and Tweed, C.J. 1990 Modelling and experimental studies of sorption in the near field of a cementitious repository. Scientific Basis for Nuclear Waste Management XIII (eds. V.M. Oversby and P.W. Brown), Mat. Res. Soc. Symp. Proc. Vol. 176, pp591-598. Materials Research Society, Pittsburgh {2}
  • Chambers, A.V. 1995 Modelling Radionuclide Transport in Cracks through Cemented Radioactive Waste. Scientific Basis for Waste management XVIII (eds. T. Murakami and R.C. Ewing), Mat. Res. Soc. Symp. Proc. Vol 353, Part 2, pp 891-898, Materials Research Society, Pittsburgh {10, 15}
  • Curti, E. 1999 Co-precipitation of radionuclides with calcite: estimation of partition coefficients based on a review of laboratory investigations and geochemical data. Applied Geochemistry, 14, 433-445 {3}
  • Gérard B. and Marchand J. 2000 Influence of cracking on the diffusion properties of cement-based materials. Part I: Influence of continuous cracks on the steady-state regime. Cement and Concrete Research, 30, 37-43 {6}
  • Idemitsu, K., Furaya, H., Hara, T. and Inagaki, Y. 1991 Migration of cesium, strontium and cobalt in water saturated concretes. Mat. Res. Soc. Symp. Proc., 212, 427-432 {2}
  • Johannesson, B.F. 1999 Diffusion of a mixture of cations and anions dissolved in water. Cement and Concrete Research, 29, 1261-1270 {6}
  • Johannesson, B.F. 2003 A theoretical model describing diffusion of a mixture of different types of ions in pore solution of concrete coupled to moisture transport. Cement and Concrete Research, 33, 481-488 {6}
  • Johnston, H.M. and Wilmot, D.J. 1992 Sorption and diffusion studies in cementitious grouts. Waste Management, 12, 289-297 {2, 6}
  • Kempe, T., Gierszewski, P., Heystee, R., Jensen, M. and Leung, H. 2007 Developing a safety case for Ontario Power generation’s L&ILW Deep Geologic Repository. NEA/EC/IAEA Symp on Safety Cases for the Deep Disposal of Radioactive Wastes. Paris, France. {24}
  • Locoge, P., Massat, M., Ollivier, J.P. and Richet, C. 1992 Ion diffusion in microcracked concrete. Cement and Concrete Research, 22/2-3, 431-438 {6}
  • McKinley, I.G. and Savage, D. 1996 Comparison of solubility databases used for HLW performance assessment. J. Contaminant Hydrology, 21, 335-350 {13}
  • McKinley, I.G. and Scholtis, A. 1993 A comparison of radionuclide sorption databases used in recent performance assessments. J. Contaminant Hydrology, 13, 347-363 {3}
  • Muurinen A. et al. 1983 Diffusion measurements in concrete and compacted bentonite. Scientific Basis for Nuclear Waste Management. Mat. Res. Soc. Symp. Proc. Vol. 15, pp777-784. Materials Research Society, Pittsburgh {5, 6}
  • Muurinen, A., Rntanen, J. and Ovaskainen, R. 1985 Diffusivities of cesium and strontium in concretes and in mixtures of sodium bentonite and crushed rock. Mat. Res. Soc. Symp. Proc., 44: 883-890 {5, 6}
  • Ngala, V.T. and Page, C.L. 1997 Effects of carbonation of pore structure and diffusional properties of hydrated cement pastes. Cement and Concrete Research, 27(7) 995-1007 {6}
  • Ochs, M., Hager, D., Helfer, S. and Lothenbach, B. 1997 Solubility of radionuclides in fresh and leached cementitious systems at 22°C and 50°C. Scientific Basis for Nuclear Waste Management XXI (eds. I.G. McKinley and C. McCombie). Mat. Res. Soc. Symp. Proc. Vol. 506, pp773-780. Materials Research Society, Pittsburgh {13}
  • Sarott, F.-A., Bradbury, M.H., Pandolfo, P. and Spieler, P. 1992 Diffusion and adsorption studies on hardened cement paste and the effect of carbonation on diffusion rates. Cement and Concrete Research, 22/2-3, 439-444 {2, 6, 10}
  • Savage, D. 1995 The geochemical behaviour of nickel in the repository environment. Scientific Basis for Waste management XVIII (eds. T. Murakami and R.C. Ewing). Mat. Res. Soc. Symp. Proc. Vol. 353, pp1159-1166. Materials Research Society, Pittsburgh {13}
  • Savage, D. (ed) 1995 The Scientific and Regulatory Basis for the Geological Disposal of Radioactive Waste. J Wiley, London. ISBN: 047196090X 454pp. {24}
  • Serne, R.J., Lokken, R.O. and Criscenti, L.J. 1992 Characterization of grouted low-level waste to support performance assessment. Waste Management, 12: 271-287 {24}
  • Serne, R.J., Rai, D., Martin, P.F., Felmy, A.R., Rao, L. and Ueta, S. 1996 Leachability of Nd, U, Th and Sr from cements in a CO2 free atmosphere. Scientific Basis for Nuclear Waste Management XIX (eds. W.M. Murphy and D.A. Knecht). Mat. Res. Soc. Symp. Proc. Vol 412. pp 459-467. Material Research Society, Pittsburgh {13}
  • Shimooka K. et al. 1989 Performance experiment of LLRW disposal concrete vault – Migration behaviour of radionuclides in backfill and concrete. Japan Atomic Energy Research Institute, Ibaraki. In: International Waste Management Conference, Kyoto, 1989. Volume 2 {2, 6}
  • Wang, K. Jansen, D.C. and Shah, S.P. 1997 Permeability study of cracked concrete. Cement and Concrete Research, 27(3) 1515-1524 {15}

Tags:

  • radioactive
  • reference
  • waste
Have more questions? Submit a request

Comments