Din avgränsning ger 495 träffar.
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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 -
2010:25 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 -
2010:18 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 -
2010:09 Copper Thermodynamics in the Repository Environment up to 130˚C
The mechanisms of copper corrosion for a KBS-3 repository for spent nuclear fuel need to be known with a high level of confidence. This is because the overall rate of copper canister corrosion (accounting for corroding species concentrations, geochemical conditions and the mass transport through surrounding barriers) provides an essential performance indicator in safety assessment. A...
Innehållstyp: Publikationer -
2010:05 Discrete-Feature Model Implementation of SDM-Site Forsmark
SSM has been following the investigations of the two candidate sites for a repository for spent nuclear fuel that the Swedish Nuclear Fuel and Waste Management Company (SKB) have been undertaking. SKB has reported the results of the investigations as site descriptive models. These models will be used to underpin the safety analysis following the license application of the repository planned...
Innehållstyp: Publikationer -
2018:21 Research on Resaturation of Bentonite Buffer
Background Resaturation processes in the bentonite buffer in a KBS-3 type repository for spent nuclear fuel are complicated and are often illustrated, analysed and modelled multi-disciplinarily as coupled thermal (T), hydrological (H) and mechanical (M) processes with multi-phase flow, elastoplastic evolution in a swelling porous medium. Previous THM-modelling showed that the re-saturation...
Innehållstyp: Publikationer -
2018:23 Evaluation of the Impact of the Model Additional Protocol on Non-Nuclear-Weapon States with Comprehensive Safeguards Agreements
Background The Swedish Radiation Safety Authority (SSM) called for research proposals related to Non-Proliferation. This call resulted in SSM accepting a proposal from the Vienna Center for Disarmament and Non-Proliferation (VCDNP) to evaluate the impact of the implementation of Additional Protocols (AP). The Additional Protocol, which was approved by the International Atomic Energy Agency's...
Innehållstyp: Publikationer -
2018:01 Monte Carlo patient-specific pre-treatment QA system for volumetric modulated arc therapy
Background According to the Swedish Radiation Safety Authority's Regulations in Radiotherapy (SSMFS 2008:33) are Swedish clinics required to verify the individual dose to patients, prior the first time a new treatment is given. To fulfil this requirement, current clinics perform in-vivo dosimetry in three dimensional conformal radiation therapy (3DCRT), which means that the entrance of...
Innehållstyp: Publikationer -
2016:27 Validation of fatigue fracture mechanics approaches
Background In a previous study (SSM research report 2015:38) fatigue experiments were performed on welded austenitic stainless steel piping components. The fatigue experiments offer an opportunity to evaluate fatigue flaw tolerance assessments used in industry, which are based on the fracture mechanical approach implemented in ProSACC. Objective The present study aims to validate the used...
Innehållstyp: Publikationer -
2016:29 Evaluation of the Swedish participation in the Halden Reactor Project 2006–2014
This is a report on the evaluation of the Swedish participation in the Halden Reactor Project 2006-2014. The study has consisted in evaluating the types and extent of added value from the Swedish participation in the Halden Reactor Project, and to determine what additional added value the participation could supply for the Swedish authority. It can be concluded from the study that the impacts...
Innehållstyp: Publikationer