Din avgränsning ger 168 träffar.
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2015:46 Assessment of data and criteria for cladding burst in loss-of-coolant accidents
Ali R. Massih, Lars Olof Jernkvist SSM English...
Innehållstyp: Publikationer -
2014:20 An evaluation of high-temperature creep of zirconium alloys: data versus models
In this report Dr Massih presents correlations for creep in different phases of zirconium alloys and also presents a general solution to the difficulty of accurately describing the material properties in phase transition for several zirconium alloys. Based upon superplasticity relations, models are adapted to fit with experimental data for materials in transition regions. The creep models are...
Innehållstyp: Publikationer -
1997:05 SKI SITE-94
The Swedish Industry program for deep geological disposal of spent nuclear fuel and high-level radioactive waste is now in the early stages of the site selection process, with feasibility studies underway in 5 to 10 municipalities. According to the Swedish Nuclear Fuel and Waste Management Co., SKB (SKB RD&D Programme, 1995), the ongoing siting process involves selection of two sites for...
Innehållstyp: Publikationer -
96:41 SKIs utvärdering av SKBs FUD-program 95
Sammanställning av remissvar...
Innehållstyp: Publikationer -
96:48 SKIs utvärdering av SKBs FUD-program 95
Gransknings-PM...
Innehållstyp: Publikationer -
96:49 SKIs utvärdering av SKBs FUD-program 95
Sammanfattning och slutsatser...
Innehållstyp: Publikationer -
2013:14 Approaches used for Clearance of Lands from Nuclear Facilities among Several Countries – Evaluation for Regulatory Input
SSM has recently established new regulations for clearance of materials, rooms, buildings and land (SSMFS 2011:2). The regulations specify that license holders for practices involving ionising radiation shall take measures after the cessation of the practice to achieve clearance of rooms, buildings and land. The regulations state nuclide specific clearance levels in becquerel per m2 for rooms...
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 -
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