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2022:14 Weld residual stress and strain measurements on a mock-up with single layer strip cladding common in reactor pressure vessels
Summary Residual stress and strain measurements were performed on a mock-up consisting of a 160 mm thick low-alloy ferritic steel plate of type SA-508 Class 3 with a single layer weld deposited strip cladding of austenitic stainless steel E308L. The cladding was manufactured with submerged arc strip welding adapted to a procedure used for reactor pressure vessels in the 1970s. Comprehensive...
Content type: Publications -
Our safety and security work
The role of the Swedish Radiation Safety Authority is to impose safety and security requirements as well as to conduct follow-ups to ensure that the entities operating the facilities fulfil the applicable regulatory frameworks and requirements.
Content type: Regular Pages -
2014:07 Technical Note, Review of the geological mapping and geophysical measurement techniques for the determination of critical properties around deposition holes -Main Review Phase
This Technical Note reports the findings of a detailed evaluation of the geological and geophysical methods proposed by SKB with respect to their ability, resolution, performance, reliability and robustness to measure the geomechanical parameters critical for determining deposition hole acceptability during repository operation. Addressed are specific questions focusing on the detection of...
Content type: Publications -
2015:37 Models for axial relocation of fragmented and pulverized fuel pellets in distending fuel rods and its effects on fuel rod heat load
Haverifall med kylmedelsförlust (LOCA) i lättvattenreaktorer kan leda till överhettning av bränslestavar, utvidgning av stavarnas kapslingsrör, samt axiell omflyttning av bränslekutsfragment i de delar av stavarna som expanderat. Bränsleomflyttningen kan koncentrera värmebelastningen till en begränsad del av stavarna och därigenom öka risken...
Content type: Publications -
2014:17 Technical Note, Assessment of radiological effects on non-human biota –Main Review Phase
This report presents a review of SKBs assessment of the long-term radiological effects on plants and animals of a deep geological repository as described in SKB report TR-10-08. The SKB report is one of a number contributing to the overall safety assessment, referred to as SR-Site, for the repository. The conclusion of the SKB report was that the ‘study gives no reason to assume that any of...
Content type: Publications -
2013:16 Technical Note, Assessment of PWR fuel depletion and of neutron multiplication factors for intact PWR fuel copper canisters – main review phase
SKB (Svensk Kärnbränslehantering AB) in 2011 applied to the Swedish government for approval of a proposed solution for disposal of used fuel from Swedish nuclear power reactors and some relatively minor quantities of other fissile material. This Technical Note contains results of a recent review of the SKB methods used to determine the influence of reactor depletion on keff of intact...
Content type: Publications -
2015:40 Technical Note, Assessment of flow-related transport parameters used in the SR-Site safety case
Joel E. Geier SSM English...
Content type: Publications -
2015:41 Technical Note, Hydrogeological aspects of future human actions for a repository at Forsmark
Joel E. Geier SSM English...
Content type: Publications -
2015:45 Technical Note, Parallel assessment of effects on non-human biota using RESRAD-BIOTA
Karolina Stark SSM English...
Content type: Publications -
2012:35 Technical Note, Review of SKB’s Code Documentation and QA for the SR-Site Safety Assessment
This initial review examined the Swedish Nuclear Fuel and Waste Management Company (SKB) code documentation and quality assurance, which is important to the safety assessment SR-Site because the computer codes used must be both suitable for the analyses performed and capable of producing accurate results for those analyses. SKB has prepared a report that summarizes the code documentation...
Content type: Publications