Din avgränsning ger 127 träffar.
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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 -
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 -
SSMFS 2008:38 Strålsäkerhetsmyndighetens föreskrifter om arkivering vid kärntekniska anläggningar
I SSMFS 2008:38 har ändringar införts genom SSMFS 2020:2 och 2022:12.
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 -
2011:22 Infiltration of dilute groundwaters and resulting groundwater compositions at repository depth
The planned Swedish concept for final disposal of spent nuclear fuel includes copper canisters placed in deposition holes at about 500 m depth in granitic bedrock. The copper canisters will be surrounded by bentonite buffer with the objective of inhibiting groundwater flow adjacent to the canister. It has been discovered that dilute glacial melt-water may induce erosion of the buffer material.
Innehållstyp: Publikationer -
2012:21 Technical Note, Initial Review Phase for SKBs Safety Assessment SR-Site: Corrosion of Copper
The uniform and localized corrosion treatments as well as stress corrosion cracking positions currently considered by SKB have been examined with the objective of identifying key unresolved issues or gaps, needs and opportunities. In conjunction with the review of the SKB reports listed in Appendix 1, there has been some consideration of the broader literature. This summary highlights the...
Innehållstyp: Publikationer -
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...
Innehållstyp: Publikationer -
2011:21 Workshop on spent fuel performance and radionuclide chemistry -Rånäs 2010: Assessment of some outstanding issues
The safety assessment for final disposal of spent nuclear fuel has to comprehensively address the stage when containment barriers have failed and when radionuclide releases occur to the surrounding groundwater at repository depth. Essential processes for estimating risk/dose related to this scenario involve the release of radionuclide from the spent fuel surfaces due to radio-lytic oxidative...
Innehållstyp: Publikationer