Home Geochemically derived non-gaseous radionuclide source term for the Asse salt mine – assessment for the use of a Mg(OH)2-based backfill material
Article
Licensed
Unlicensed Requires Authentication

Geochemically derived non-gaseous radionuclide source term for the Asse salt mine – assessment for the use of a Mg(OH)2-based backfill material

  • Volker Metz , W. Schüßler , B. Kienzler and Thomas Fanghänel
Published/Copyright: September 25, 2009

Summary

The Asse salt mine was used as a test site for radioactive waste disposal from 1967 to 1978. Low- and intermediate-level waste forms (LLW/ILW) were emplaced, containing a total radionuclide inventory of 3×1015 Bq, estimated for reference date January 1, 2005. It is expected that MgCl2-rich brine will enter the emplacement rooms and react with the cemented waste products. Possible microbal degradation of organic waste components in MgCl2-rich brine could produce significant quantities of CO2, resulting in an acidification and consequently in an increase of element solubilities. Application of buffering backfill materials is discussed for closure of the mine. Selection of backfill materials is based on geochemical modeling taking into account the corrosion of the cemented LLW/ILW and degradation of organic waste components. In the present study the evolving geochemical milieu and respective solubilities of Am, Np, Pu, U, Th, Tc, Sr, Cs and I were modeled for each emplacement room. Laboratory experiments were undertaken to selectively verify the modeling predictions.

Geochemical modeling leads to the conclusion that Portland cement, a Mg(OH)2-based material and crushed salt can be used in different combinations as backfill materials. According to the predictions Mg(OH)2-based backfill material controls the pH and concentration of dissolved inorganic carbon within ranges that are favorable with respect to actinide solubilities. A source term for radioelements and fission products is derived from a comparison of the respective solubilities and the radionuclide inventories. Calculated solubilities of Th, Pu and U are lower than their inventories. These are controlled by the thermodynamic solubility therefore. Maximum solution concentrations of all other elements are controlled by their inventory.

Published Online: 2009-9-25
Published in Print: 2004-11-1

© 2004 Oldenbourg Wissenschaftsverlag GmbH

Articles in the same Issue

  1. Preface: Migration Conference 2003
  2. Actinide chemistry: from weapons to remediation to stewardship
  3. Thermodynamics and solubility of (UxNp1-x)O2(am) solid solution in the carbonate system
  4. Solubility and colloid formation of Th(IV) in concentrated NaCl and MgCl2 solution
  5. Effect of reducing agents on the uranium concentration above uranium(IV) amorphous precipitate in Boom Clay pore water
  6. On Mo-Ru-Tc-Pd-Rh-Te alloy particles extracted from spent fuel and their leaching behavior under Ar and H2 atmospheres
  7. Modeling of the complex formation of metal ions with humic acids
  8. Application of the NICA-Donnan model for proton, copper and uranyl binding to humic acid
  9. Protonation and complexation of isosaccharinic acid with U(VI) and Fe(III) in acidic solutions: potentiometric and calorimetric studies
  10. Carbonate complexation of neptunium(IV) in highly basic solutions
  11. Fluorescence characteristics of complex formation of europium(III)-salicylate
  12. The reduction of U(VI) by near field hydrogen in the presence of UO2(s)
  13. Electrochemical aspects of radiolytically enhanced UO2 dissolution
  14. Effect of alpha radiolysis on doped UO2 dissolution under reducing conditions
  15. The redox behaviour of plutonium in humic rich groundwater
  16. The fate of radiolytic oxidants during spent fuel leaching in the presence of dissolved near field hydrogen
  17. Structural changes of uranyl moiety with reduction from U(VI) to U(V)
  18. Trivalent actinide coprecipitation with powellite (CaMoO4): Secondary solid solution formation during HLW borosilicate-glass dissolution
  19. Reproducibility of the uptake of U(VI) onto degraded cement pastes and calcium silicate hydrate phases
  20. Uranium adsorption on weathered schist – intercomparison of modelling approaches
  21. Contribution of minerals to the sorption of U(VI) on granite
  22. Distribution and geochemical association of actinides in a contaminated soil as a function of grain size
  23. Interactions between anionic complex species of actinides and negatively charged mineral surfaces
  24. Measurements and modelling of Pm sorption onto TiO2 and goethite
  25. Effect of humic acid on the sorption of Cm(III) onto γ-Al2O3 studied by the time-resolved laser fluorescence spectroscopy
  26. Am(III) and Eu(III) uptake on hematite in the presence of humic acid
  27. Luminescence properties of tetravalent uranium in aqueous solution
  28. Scanning transmission X-ray microscopy as a speciation tool for natural organic molecules
  29. Formation of hydroxyapatite in soils using calcium citrate and sodium phosphate for control of strontium migration
  30. Influence of humic substances on the 63Ni migration through crushed rock media
  31. U, Th, Eu and colloid mobility in a granite fracture under near-natural flow conditions
  32. Sorption behavior of europium(III) and curium(III) on the cell surfaces of microorganisms
  33. Interactions of trivalent and tetravalent heavy metal-siderophore complexes with Pseudomonas fluorescens
  34. In-situ diffusion of HTO, 22Na+, Cs+ and I- in Opalinus Clay at the Mont Terri underground rock laboratory
  35. Results of the colloid and radionuclide retention experiment (CRR) at the Grimsel Test Site (GTS), Switzerland – impact of reaction kinetics and speciation on radionuclide migration
  36. Fracture flow and radionuclide transport in block-scale laboratory experiments
  37. Comparison between in situ and laboratory diffusion studies of HTO and halides in Opalinus Clay from the Mont Terri
  38. Solubility constraints on uranium concentrations in groundwaters of the Tono uranium deposit, Japan
  39. Mobility of uranium in tertiary argillaceous sediments – a natural analogue study
  40. Redistribution of U, Pb and REE in association with alteration of uranium minerals from the Koongarra deposit, Northern Territory, Australia
  41. Towards a common thermodynamic database for speciation models
  42. Geochemically derived non-gaseous radionuclide source term for the Asse salt mine – assessment for the use of a Mg(OH)2-based backfill material
  43. Simulation of remediation alternatives for a 137Cs contaminated soil
  44. Simulating reactive transport in time dependent multiphase flow problems
  45. Reactive transport modelling of a spent fuel repository in a stiff clay formation considering excavation damaged zones
  46. Coupled transport/reaction modelling of copper canister corrosion aided by microbial processes
Downloaded on 29.9.2025 from https://www.degruyterbrill.com/document/doi/10.1524/ract.92.9.819.54991/html?lang=en
Scroll to top button