Filtered generated 228 hits.
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2021:06 Quality Assurance Review of the Swedish Nuclear Fuel and Waste Management Company’s LOT Experiment (Phase S2 and A3) at the Äspö Facility in Sweden
SSM perspective Background This report presents a quality assurance (QA) review of the work done by SKB to retrieve the S2 and A3 parcels from the Long term test of buffer material (the LOT experiment) at the Äspö Hard Rock Laboratory. Each LOT parcel comprises a heated copper tube surrounded by bentonite, with a number of copper coupons and various other test and monitoring instruments...
Content type: Publications -
2023:10 General data in accordance with the requirements in Article 37 of the Euratom Treaty
Oskarshamn Very Low-level Radioactive Waste Disposal Facility, MLA3, Sweden...
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Notification concerning NORM
This page is intended for those who handle naturally occurring radioactive material (NORM) as waste, by-product or raw material, including building materials subject to notification. It contains information about when you have a notification obligation and how to register your operation with us.
Content type: Regular Pages -
Radioactive waste
Radioactive waste is generated in activities where radioactive substances are used. The largest amount is generated in Swedish nuclear power plants. Some of the radioactive waste comes from other activities involving radiation, such as healthcare, research and industrial operations. Radioactive waste is generated, for example, when end-of-life fire detectors have to be disposed of, in...
Content type: Regular Pages -
2009:19 Review of SKB’s Quality Assurance Programme
SKB is preparing a license application for the construction of a final repository for spent nuclear fuel in Sweden. This application will be supported by the safety assessment SR-Site for the post-closure phase. The assessment of long-term safety is based on a broad range of experimental results from laboratory scale, intermediate scale and up to full scale experiments. It is essential that...
Content type: Publications -
2009:09 Analysis of three sets of SWIW tracer test data using a two-population complex fracture model for matrix diffusion and sorption
For the non-sorbing tracer uranine, both the finite and the semi-infinite populations play a distinct role in controlling BTC. For the sorbing tracers Cs and Rb the finite population does not saturate, but acts essentially semi-infinite, thus the BTC behaviour is comparable to that obtained for a model containing only a semi-infinite rock matrix. The ability to match BTC for both sorbing and...
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...
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Research on nuclear materials and waste to be strengthened with new partnerships within the EU
Two new major partnerships for research on materials in nuclear energy and nuclear waste management have been launched this autumn. The Swedish Radiation Safety Authority (SSM) actively participates in the partnerships and also contributes with research funds to projects that are granted funding. A total of three partnerships are now ongoing, distributing altogether 70 million euros over a...
Content type: News -
2011:16 Modelling of ultrasonic testing of cracks in cladding
During the last two decades, SSM has supported research to develop a model for the non-destructive test situation based on ultrasonic technique. Such a model is important in many ways, for example to supplement and plan experimental studies and to perform parametric studies in qualification situation. Modeling can be a useful tool when the inspection system shall be technically justified.
Content type: Publications -
2013:24 Modelling of nuclear fuel cladding under loss-of-coolant accident conditions
We present a unified model for calculation of zirconium alloy fuel cladding rupture during a postulated loss-of-coolant accident in light water reactors. The model treats the Zr alloy solid-to-solid phase transformation kinetics, cladding creep deformation, oxidation and rupture as a function of temperature and time in an integrated fashion during the transient. The fuel cladding material...
Content type: Publications