Din avgränsning ger 569 träffar.
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2008:10 International Expert Review of SR-Can: Engineered Barrier Issues
The Swedish Nuclear Fuel and Waste Management Company (SKB) has recently submitted a license application for the construction of a spent fuel encapsulation plant. SKB plans to submit a further license application in 2009 for the construction of a repository for the disposal spent nuclear fuel. In connection with the first of these applications, SKB published a safety report, known as SR-Can,...
Innehållstyp: Publikationer -
2008:03 Myndigheternas granskning av SKB:s preliminära säkerhetsbedömningar för Forsmark och Laxemar
Detta dokument redovisar SKI:s och SSI:s granskning av SKB:s preliminära säkerhetsbedömningar för Forsmark och Laxemar. Myndigheternas syfte med denna granskning är att bedöma om SKB:s inledande platsundersökningar har tillräcklig omfattning, håller tillräckligt hög kvalitet och omfattar de data som behövs för kommande säkerhetsanalyser.
Innehållstyp: Publikationer -
2007:32 Low pH Cements
Concrete and cement are used in constructions as well as in conditioning of waste in repositories for radioactive waste. The development of low pH cements for use in geological repositories for radioactive waste stem from concerns over the potential for deleterious effects upon the host rock and other EBS materials (notably bentonite) under the hyperalkaline conditions (pH > 12) of cement...
Innehållstyp: Publikationer -
2008:16 Review of SKB:s Safety Assessment SR-Can: Contributions in Support of SKI:s and SSI:s Review by External Consultants
The work presented in this report is part of the Swedish Nuclear Power Inspectorate’s (SKI) and the Swedish Radiation Protection Authority’s (SSI) SR-Can review project. The Swedish Nuclear Fuel and Waste Management Co (SKB) plans to submit a license application for the construction of a repository for spent nuclear fuel in Sweden 2010. In support of this application SKB will present a safety...
Innehållstyp: Publikationer -
2007:29 Intercomparison of Cement Solid-Solution Models
Many concepts for the geological storage of radioactive waste incorporate cement based materials, which act to provide a chemical barrier, impede groundwater flow or provide structural integrity of the underground structures. Thus, it is important to understand the long-term behaviour of these materials when modelling scenarios for the potential release and migration of radionuclides. In the...
Innehållstyp: Publikationer -
2007:10 DECOVALEX-THMC - Task D
The DECOVALEX project is an international cooperative project initiated by SKI, the Swedish Nuclear Power Inspectorate, with participation of about 10 international organizations. The name DECOVALEX stands for DEvelopment of COupled models and their VALidation against Experiments. The general goal of this project is to encourage multidisciplinary interactive and cooperative research on...
Innehållstyp: Publikationer -
2014:57 Technical Note, Issues in the Corrosion of Copper in a Swedish High Level Nuclear Waste Repository: Phase III. Role of Sulphide Ion in Anodic and Cathodic Processes
The most important findings of this research project show that: In the case when the bentonite buffer between the copper canister and the granitic rock is not damaged, we can neglect the possibility of general corrosion damage being a threat to canister integrity over a 100,000 year storage period. However, if the bentonite buffer is damaged for any reason, and does not act as an engineered...
Innehållstyp: Publikationer -
2014:48 Technical Note, Independent assessment of groundwater sulphide content in the long-te
Groundwater sulphide content is a key factor in the determination of canister lifetimes because of its role in corrosion of copper. SKB has based the canister lifetime analysis on a distribution of measured sulphide concentrations which are assumed to apply throughout the long-term analysis period. The distribution is based on expert judgement in the selection of samples that are regarded as...
Innehållstyp: Publikationer -
2014:50 Technical Note, A Study of Availability of Fuel Data for Sweden’s Spent Nuclear Fuel
The study covers all types spent fuel planned to be placed in the final repository. It was carried out by selecting a sample of spent fuel and investigating the information available at the Nuclear Power Plants (NPP’s) in Sweden, the Central interim storage facility (Clab) and Studsvik. The results indicate that the required data is available and can be obtained for fuel unloaded after 1980.
Innehållstyp: Publikationer -
2014:41 Technical Note, Review of Radionuclide Abstraction and Selection in the SKB Safety Case -Main Review Phase
As part of the Swedish Radiation Safety Authority (SSM) review of the Swedish Nuclear Fuel and Waste Management Company (SKB) SR-Site safety assessment for a spent nuclear fuel repository in Sweden, this technical note documents the Center for Nuclear Waste Regulatory Analyses (CNWRA®) review of the abstraction and selection of radionuclides in the SKB safety case. Specifically, CNWRA...
Innehållstyp: Publikationer