Din avgränsning ger 267 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 -
2013:24 Modelling of nuclear fuel cladding under loss-of-coolant accident conditions
We present a unified model for calculation of zirconium alloy fuel cladding rupture during a postulated loss-of-coolant accident in light water reactors. The model treats the Zr alloy solid-to-solid phase transformation kinetics, cladding creep deformation, oxidation and rupture as a function of temperature and time in an integrated fashion during the transient. The fuel cladding material...
Innehållstyp: Publikationer -
Kompletteringar (SFR)
Här listas de kompletteringar som SKB gjort till ansökan enligt kärntekniklagen, daterad 19 december 2014, indelade per tillfälle då de skickades in.
Innehållstyp: Artiklar -
Strålsäkerhetsmyndighetens svar på regeringens remisser
Regeringen fattade beslut om att godkänna ett slutförvar för använt kärnbränsle i januari 2022. Strålsäkerhetsmyndigheten svarade på regeringens remisser 2019–2021 inför beslutet. ...
Innehållstyp: Artiklar -
2014:50 Technical Note, A Study of Availability of Fuel Data for Sweden’s Spent Nuclear Fuel
The study covers all types spent fuel planned to be placed in the final repository. It was carried out by selecting a sample of spent fuel and investigating the information available at the Nuclear Power Plants (NPP’s) in Sweden, the Central interim storage facility (Clab) and Studsvik. The results indicate that the required data is available and can be obtained for fuel unloaded after 1980.
Innehållstyp: Publikationer -
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 -
2014:22 Technical Note, Workshop on seismic hazard at Forsmark
This report describes the outcome of the workshop organized by SSM on seismic hazard at Forsmark that was held in Stockholm on the 4 and 5 of June, 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 -
2013:35 Technical Note, Rock Mechanics – Confidence of SKB’s models for predicting the occurrence of a damage zone around the excavations – Main Review Phase
This assignment, performed at Southwest Research Institute, focusses on evaluating SKB’s assessment of potential occurrence of damaged rock zones (also referred to as excavation-damaged zone or EDZ) around underground excavations at the site. This report presents the authors’ evaluation of SKB’s assessment in the specific area based on questions raised by SSM. The evaluation includes...
Innehållstyp: Publikationer -
2012:53 Technical Note, Review of Engineering Geology and Rock Engineering aspects of the operation and closure of a KBS-3 repository at the Forsmark site – Initial Review Phase
SRK Consulting (UK) Limited (SRK) has reviewed the Engineering Geology and Rock Engineering aspects of the operation and closure of a KBS-3 repository at the Forsmark site in Sweden. The review assignment is part of a Swedish Radiation Safety Authority (SSM) Initial Review Phase. The review was carried out by David Saiang (PhD) on behalf of SRK. Therefore some of the views expressed in the...
Innehållstyp: Publikationer -
2012:48 Technical Note, Use of Solubility Limits in the SR-Site Safety Assessment
In a radioactive waste disposal environment, in some potential situations (scenarios) a disposed canister containing spent fuel may be breached and the fuel may come into contact with groundwater. The concentration of a radioactive element such as uranium may rise to a level where the solution is saturated. No more of the radioactive element may dissolve and a precipitated solid may be formed.
Innehållstyp: Publikationer