Filtered generated 161 hits.
-
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...
Content type: Publications -
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.
Content type: Publications -
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...
Content type: Publications -
1997:05 SKI SITE-94
The Swedish Industry program for deep geological disposal of spent nuclear fuel and high-level radioactive waste is now in the early stages of the site selection process, with feasibility studies underway in 5 to 10 municipalities. According to the Swedish Nuclear Fuel and Waste Management Co., SKB (SKB RD&D Programme, 1995), the ongoing siting process involves selection of two sites for...
Content type: Publications -
2015:46 Assessment of data and criteria for cladding burst in loss-of-coolant accidents
Ali R. Massih, Lars Olof Jernkvist SSM English...
Content type: Publications -
2020:01 Sulphide-induced stress corrosion cracking and hydrogen absorption incopper exposed to sulphide and chloride containing deoxygenated water at 90°C
SSM perspective Background The concept that the Swedish nuclear power industry plans to utilise for the final disposal spent nuclear fuel is called KBS-3 method, which is based on three different barriers to prevent spreading of radioactive substances: copper canisters, bentonite buffers and the surrounding Swedish bedrock. In the current KBS-3 design, the spent nuclear fuel will be placed in...
Content type: Publications -
2013:28 Brine intrusion by upconing for a high-level nuclear waste repository at Forsmark. Scoping calculations
SSM currently reviews a license application for a spent nuclear fuel repository that is proposed to be located at Forsmark, Sweden. The repository is to be situated at 500 m depth in the rock and copper canisters are deposited in holes excavated from the tunnel system. To protect the canisters they are surrounded by a bentonite clay buffer, which is to swell when getting in contact with...
Content type: Publications -
2013:36 Technical Note, Review and assessment of aspects of the Qeq concept – Main Review Phase
This technical review assignment considers the models and abstractions that Swedish Nuclear Fuel and Waste Management Company (SKB) developed to represent transport of dissolved constituents in the near field at the Forsmark site, in particular the Qeq abstraction for diffusive transport. SKB uses the Qeq parameter to scale concentration gradients in order to estimate dissolved-species fluxes...
Content type: Publications -
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...
Content type: Publications -
2013:35 Technical Note, Rock Mechanics – Confidence of SKB’s models for predicting the occurrence of a damage zone around the excavations – Main Review Phase
This assignment, performed at Southwest Research Institute, focusses on evaluating SKB’s assessment of potential occurrence of damaged rock zones (also referred to as excavation-damaged zone or EDZ) around underground excavations at the site. This report presents the authors’ evaluation of SKB’s assessment in the specific area based on questions raised by SSM. The evaluation includes...
Content type: Publications