Nuclear Waste Disposal in Deep Geological Formations: What are the Major Remaining Scientific Issues?
Creators
- 1. Scientific Direction, INERIS, Parc Technologique ALATA, BP2, Verneuil-en-Halatte, 60550, (France)
- 2. Institut des Sciences Analytiques, Universite de Lyon, 43 avenue du 11 novembre 1918, Villeurbanne, 69622 (France)
Description
For more than thirty years, considerable efforts have been carried out in order to evaluate the possibility of disposing of high level wastes in deep geological formations. Different rock types have been examined, such as water-under-saturated tuffs (USA), granites or crystalline rocks (Canada, Sweden, and Finland), clays (France, Belgium, and Switzerland), rock-salt (Germany). Deep clays and granites, (provided that the most fractured zones are avoided in the second case) are considered to fulfill most allocated functions, either on short term (reversibility) or long term. Chemically reducing conditions favor the immobilization of actinides and most fission products by precipitation, co-precipitation and sorption. If oxidizing conditions prevail, the safety demonstration will mostly rely on the performance of artificial confinement systems. Rock-salt offers limited performance considering the issue of reversibility, which is now perceived as essential, mostly for ethical and sociological reasons. However, several issues would deserve additional research programs, and as a first priority, a clear description of time/space succession of processes during the evolution of the repository. This will allow a better representation of coupled processes in performance assessment, such as the influence of gases (H2) generated by corrosion, on the long term dynamics of the re-saturation. Geochemical interactions between the host formation and the engineered systems (packages + barriers) are still insufficiently described. Additional gains in performance could be obtained when taking into account processes such as isotopic exchange. Imaginative solutions, employing ceramic- carbon composite materials could be proposed to replace heavy and gas-generating overpacks, or to accommodate the small but probably significant amount of 'ultimate' wastes that will be inevitably produced by Generation IV reactor systems. (author)
Additional details
Publishing Information
- Publisher
- Materials Research Society - MRS
- Imprint Place
- Warrendale (United States)
- ISBN
- 978-1-55899-942-8
- Imprint Title
- Proceedings of the symposium on Scientific Basis for Nuclear Waste Management XXX
- Imprint Pagination
- v. 985, 663 p.
- Journal Page Range
- p. 219-226
- CODEN
- MRSPDH
Conference
- Title
- Symposium on Scientific Basis for Nuclear Waste Management
- Dates
- 27 Nov - 1 Dec 2006
- Place
- Boston - Massachusetts (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 39077226
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CLAYS; CONFINEMENT; COPRECIPITATION; CORROSION; FISSION PRODUCTS; GEOLOGIC FORMATIONS; GRANITES; HIGH-LEVEL RADIOACTIVE WASTES; ISOTOPIC EXCHANGE; METAMORPHIC ROCKS; RADIOACTIVE WASTE DISPOSAL; SALT DEPOSITS; TUFF
- Descriptors DEC
- CHEMICAL REACTIONS; GEOLOGIC DEPOSITS; IGNEOUS ROCKS; ISOTOPES; MANAGEMENT; MATERIALS; MINERALS; PLUTONIC ROCKS; PRECIPITATION; RADIOACTIVE MATERIALS; RADIOACTIVE WASTE MANAGEMENT; RADIOACTIVE WASTES; ROCKS; SEPARATION PROCESSES; SILICATE MINERALS; VOLCANIC ROCKS; WASTE DISPOSAL; WASTE MANAGEMENT; WASTES
Optional Information
- Notes
- 26 refs.