Din avgränsning ger 168 träffar.
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2014:33 Technical Note, Reproduction of SKB’s Canister Failure Calculations - What-If and ‘Residual’ Scenario to Illustrate Barrier Functions
The Swedish Nuclear Fuel and Waste Management Company (SKB) included analysis of a range of scenarios in its SR-Site report. SKB grouped these scenarios into two categories—main and residual. The main scenario included a likely scenario (corrosion failure) and a less probable scenario (seismicity-induced shear failure). The residual scenario included two unlikely scenarios—isostatic-load and...
Innehållstyp: Publikationer -
2014:48 Technical Note, Independent assessment of groundwater sulphide content in the long-te
Groundwater sulphide content is a key factor in the determination of canister lifetimes because of its role in corrosion of copper. SKB has based the canister lifetime analysis on a distribution of measured sulphide concentrations which are assumed to apply throughout the long-term analysis period. The distribution is based on expert judgement in the selection of samples that are regarded as...
Innehållstyp: Publikationer -
2014:23 Technical Note, Workshop on Rock Mechanics Issues and their Implications for Groundwater Flow – Main Review Phase
This report describes the outcome of the workshop organized by SSM on Rock Mechanics and Hydrogeology that was held in Stockholm on the 30/9 and 1/10, 2013. The report summarizes the issues discussed and extracts the essential viewpoints that have been expressed. It should not be considered as a comprehensive record of all the discussions at the workshop and individual statements made by...
Innehållstyp: Publikationer -
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...
Innehållstyp: Publikationer -
SSMFS 2008:1 Strålsäkerhetsmyndighetens föreskrifter och allmänna råd om säkerhet i kärntekniska anläggningar
I SSMFS 2008:1 har ändringar förts in genom SSMFS 2010:3, 2011:3, 2014:3, 2017:1, 2018:12, 2022:1, 2022:2 och 2023:4.
Innehållstyp: Publikationer -
2020:01 Sulphide-induced stress corrosion cracking and hydrogen absorption incopper exposed to sulphide and chloride containing deoxygenated water at 90°C
SSM perspektiv Bakgrund Den metod som den svenska kärnkraftsindustrin planerar att tillämpa för att slutförvara använt kärnbränsle kallas för KBS-3 och bygger på tre skyddsbarriärer: kopparkapslar, bentonitbuffert och det svenska urberget. I den aktuella KBS-3-utformningen kommer det använda kärnbränslet att placeras i en insats...
Innehållstyp: Publikationer -
2022:07 Översyn av lokala säkerhetsnämnder
Sammanfattning Enligt regleringsbrevet för budgetåret 2022 avseende Strålsäkerhetsmyndigheten (SSM) ska myndigheten se över syftet och uppdraget för de lokala säkerhetsnämnderna samt föreslå författningsändringar som behövs, exempelvis i förordningen (2007:1054) med instruktion för lokala säkerhetsnämnder vid...
Innehållstyp: Publikationer -
2022:11 Kingdom of Sweden IRRS ARM Summary Report 2022
The IAEA Integrated Regulatory Review Service Mission to Sweden in November 2022...
Innehållstyp: Publikationer -
2023:11 Study of degradation of spent fuel’s structural material and core components under long-term wet storage
SSM perspective Background Sweden is managing the spent nuclear fuel and core components from its commercial nuclear reactors with a national strategic plan. The fuel and core components are initially stored at the reactor site. After an on-site storage period to comply with transportation limits on decay heat and radiation, these materials are shipped to the Clab (Central Interim Storage...
Innehållstyp: Publikationer -
2023:14 Effect of gamma-irradiation on the redox states of the structural iron in bentonite clay
SSM perspective Background Bentonite clay is used as buffer and backfill material which form engineered barrier in the spent fuel repository. The buffer material surrounding the copper canister will be exposed to gamma and neutron radiations, especially during the first few hundred years after closure of the repository. The redox states of the structural iron in montmorillonite, the dominant...
Innehållstyp: Publikationer