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2019:22 Technical Note, SSM’s external experts’ reviews of SKB’s report on supplementary information on canister integrity issues
SSM perspective Background The Swedish Radiation Safety Authority (SSM) reviews the Swedish Nuclear Fuel Company’s (SKB) applications under the Act on Nuclear Activities (SFS 1984:3) for the construction and operation of a repository for spent nuclear fuel and for an encapsulation facility. As part of the review, SSM commissions consultants to carry out work in order to obtain information on...
Content type: Publications -
International peer review of repository application
The Swedish Radiation Safety Authority has performed a review of SKB’s (i.e. Svensk Kärnbränslehantering AB) application for construction of a repository for spent nuclear fuel, and recommends approval of this application, as stated in our pronouncement to the Government on 23 January 2018. A peer review has also been performed by OECD’s Nuclear Energy Agency (NEA) concerning the...
Content type: Regular Pages -
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 -
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 -
2014:20 An evaluation of high-temperature creep of zirconium alloys: data versus models
In this report Dr Massih presents correlations for creep in different phases of zirconium alloys and also presents a general solution to the difficulty of accurately describing the material properties in phase transition for several zirconium alloys. Based upon superplasticity relations, models are adapted to fit with experimental data for materials in transition regions. The creep models are...
Content type: Publications -
2013:14 Approaches used for Clearance of Lands from Nuclear Facilities among Several Countries – Evaluation for Regulatory Input
SSM has recently established new regulations for clearance of materials, rooms, buildings and land (SSMFS 2011:2). The regulations specify that license holders for practices involving ionising radiation shall take measures after the cessation of the practice to achieve clearance of rooms, buildings and land. The regulations state nuclide specific clearance levels in becquerel per m2 for rooms...
Content type: Publications -
Pronouncement on repository applications made to the Swedish Government
On 23 January 2018, the Swedish Radiation Safety Authority, SSM, in its capacity as a preparatory authority, submitted its pronouncement to the Government regarding SKB's licence applications for final disposal of spent nuclear fuel. SSM recommends approval of SKB's applications under the Act on Nuclear Activities for licences to construct a repository for spent nuclear fuel, located at...
Content type: Regular Pages -
2017:02 Slow strain rate testing of copper in sulfide rich chloride containing deoxygenated water at 90 °C
Background Stress corrosion cracking (SCC) can occur in materials from the combined influence of tensile stress and a corrosive environment. It has previously been shown in the literature, that copper can be sensitive to SCC in the presence of sulfide containing water. Since both tensile stresses are present as well as a material were SCC can occur, SCC could potentially be a problem for the...
Content type: Publications -
2017:18 FEM analysis of the mechanical integrity for the canister intended for storage of spent nuclear fuel with regard to copper creep ductility
Background For final storage of spent nuclear fuel it is suggested by the Swedish nuclear fuel and waste management company (SKB) to emplace the nuclear fuel into copper canisters which are surrounded by bentonite clay at approximately 500 meters’ depth into granitic rock. After emplacement of the canisters Bentonite swelling due to water saturation and hydrostatic pressure build up the...
Content type: Publications -
2016:16 Technical Note, Possible influence from stray currents from high voltage DC power transmission on copper canisters
Main Review Phase Introduction As part of the Swedish Radiation Safety Authority’s (SSM) review of the Swedish Nuclear Fuel and Waste management company (SKB) license application for a final storage for spent nuclear fuel, SSM has asked for complementary information regarding the effect of stray currents from high voltage cables on copper corrosion (SSM 2012). SKB therefore has performed an...
Content type: Publications