Filtered generated 160 hits.
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2012:47 C-14 Long-Term Dose Assessment: Data Review, Scenario Development, and Model Comparison
BIOPROTA (www.bioprota.org) is an international collaboration forum which seeks to provide a transparent and traceable basis for the choices of parameter values, as well as for the wider interpretation of information used in assessments. Particular emphasis is placed on data required for the assessment of long-lived radionuclide migration and accumulation in the biosphere, and the associated...
Content type: Publications -
2012:62 Technical Note, Review of the MARFA Code
As part of SSM’s Initial Review Phase of SKB’s SR-Site safety assessment of the final disposal of spent nuclear fuel at the Forsmark site, Quintessa has been requested by SSM to review SKB’s MARFA code and consider whether the technical arguments and assumptions used for developing the code are sound, appropriate and adequate to support its use in SR-Site. This Technical Note summarises the...
Content type: Publications -
2012:15 Technical Note, A review of the mechanical integrity of the canister
An introductory review of SR-Site has been conducted with respect to the mechanical integrity of the canister. The review is focused on the copper canister and the nodular cast iron insert. Review results show that a number of loads and loading scenarios for the copper canister has not been analysed by SKB. The importance of sufficient creep ductility of the copper material and sufficient...
Content type: Publications -
2012:25 Workshop on Seismology
This report summarizes the issues discussed at the workshop and extracts the essential viewpoints that have been expressed. The report is not to consider as a comprehensive record of all the discussions at the workshop and individual statements made by workshop participants should be regarded as opinions rather than proven facts. This report includes, apart from the workshop synthesis, the...
Content type: Publications -
2013:27 Numerical simulations of headed anchors break in reinforced and non-reinforced concrete structures
The design codes for anchorage of equipment in concrete structures have been developed since the time the Swedish power plants were designed. Furthermore, the design basis has been updated and in some cases new mechanical loads have been added. As a consequence, it can be difficult for some anchorages to meet the requirements of today. In the design of anchorage equipment the beneficial effect...
Content type: Publications -
2019:24 SSM's external experts' review of SKB's analysis of long-term safety of 1BMA (SFR)
SSM perspective Background Fractures in the concrete barrier of the rock vault 1BMA in the final repository for low and intermediate level waste (SFR) have been observed. The Swedish Radiation Safety Authority (SSM) enforced Swedish Nuclear Fuel and Waste Management Company (SKB) to assess the long-term radiological consequences of 1BMA (SSM2015-2432-26) given the present state of the rock...
Content type: Publications -
International radiation safety course in Stockholm gives participants practical knowledge
With radiation protection experts from all over the world and a focus on practical exercises and case studies, International Radiological Protection School (IRPS) gives professionals from over 20 different countries the opportunity for increased understanding of international radiation protection issues.
Content type: News -
2016:12 SSM’s external experts’ reviews of SKB’s safety assessment SR-PSU – engineered barriers, engineering geology and chemical inventory
Background The Swedish Radiation Safety Authority (SSM) received an application for the expansion of SKB's final repository for low and intermediate level waste at Forsmark (SFR) on the 19 December 2014. SSM is tasked with the review of the application and will issue a statement to the government who will decide on the matter. An important part of the application is SKB's assessment of...
Content type: Publications -
Technical Note
Tecnical Note About Technical Note Under the Act on Nuclear Activities, the Swedish Radiation Safety Authority (SSM) reviews SKB’s applications concerning a repository for spent nuclear fuel and an encapsulation facility. As part of this review work, SSM commissions consultants to obtain information and provide expert opinions on specific issues. SSM’s Technical Note series reports on these...
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