Din avgränsning ger 496 träffar.
-
2010:25 Modelling Coupled Processes in the Evolution of Repository Engineered Barrier Systems using QPAC-EBS
Currently in Sweden, the SR-Site safety assessment for a spent nuclear fuel repository is being developed by the Swedish Nuclear Fuel and Waste Management Company (SKB). The planned SSM review of this work requires access to a sufficient modelling capability to assess the combined performance of the engineered barriers (spent fuel canister, buffer and backfill) and the natural geosphere...
Innehållstyp: Publikationer -
2010:24 On Cost Estimate for Decommissioning of one Isotope Central
The present generation has the responsibility to ensure and guarantee that sufficient financial resources are accrued into the Swedish Nuclear Waste Fund to cover all future costs. Thus, the next generation, as well as any succeeding generations, will have the financial resources required in order to undertake the necessary measures, in an appropriate manner, for the decommissioning and...
Innehållstyp: Publikationer -
2010:18 Radionuclide Transport: Preparation During 2009 for the SR-Site Review
Post-closure safety assessments for nuclear waste repositories involve radioecological modelling for an underground source term. Following several decades of research and development, the Swedish Nuclear Waste Management Company (SKB) is approaching a phase of license application. According to SKB’s plans, an application to construct a geological repository will be submitted by the end of...
Innehållstyp: Publikationer -
2008:12 Independent Calculations for the SRCan Assessment
External review contribution in support of SKI's and SSI's review of SR-Can 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...
Innehållstyp: Publikationer -
2007:21 On tentative decommissioning cost analysis with specific authentic cost calculations with the application of the Omega code on a case linked to the Intermediate storage facility for spent fuel in Sweden
The aim of this applied study has been to demonstrate how a cost calculation is done in a systematic way. The framework of the project has been limited to older nuclear installations in Sweden. Furthermore, it may be envisaged that the process of making regular estimates of all the parameters is crucial in preparatory phases of decommissioning and dismantling processes. A secondary aim of the...
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 -
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 -
2013:28 Brine intrusion by upconing for a high-level nuclear waste repository at Forsmark. Scoping calculations
The objective of this study is to evaluate the possibility of salt-water migration to the spent nuclear repository. This objective is motivated by the adverse impacts of water with too high salinity entering the repository and by the uncertainty of the relevant hydraulic and hydrogeochemical conditions at the Forsmark site at great depths. To analyse density dependent flow and salt transport...
Innehållstyp: Publikationer -
2012:71 Identification of Brittle Deformation Zones and Weakness Zones
In preparation for the review of Swedish Nuclear Fuel and Waste Management Company’s (SKB) license application for disposal of spent nuclear fuel, Swedish Radiation Safety Authority (SSM) is conducting studies to evaluate the performance of the multi-barrier principle on which the KBS-3 concept is based. Copper canisters containing the spent nuclear fuel are placed into granitic bedrock at...
Innehållstyp: Publikationer