Din avgränsning ger 1354 träffar.
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2015:05 Technical Note, Review of uncertainty propagation and sensitivity analysis in SR-Site Main Review Phase
The review assignment SSM2014-2060 “Review of uncertainty and sensi- tivity analysis in SR-Site” addressed three issues: Adequacy of the methods adopted by SKB for conducting sensitivity analyses Approach for use of conservative and best-estimate parameter values Propagation of uncertainty for the corrosion scenario Adequacy of the methods for sensitivity analyses: The sensitivity analyses...
Innehållstyp: Publikationer -
2014:59 Technical Note, Relation between earthquake magnitude, fracture length and fracture shear displacement in the KBS-3 repository at Forsmark – Main Review Phase
This study addresses one of several scenarios that could impair the physical integrity of the repository of spent nuclear fuel at the Forsmark site. Two sources of threat are: i) events due to thermal loading on the rock mass by the heat from canisters with spent nuclear fuel, and ii) seismic events, i.e. earthquakes, at the nearby deformation zones and zones intersecting the repository area.
Innehållstyp: Publikationer -
2014:46 Technical Note, QA in SKB’s Groundwater Flow Modelling
The general objective of the project is to provide review comments on SKB’s postclosure safety analysis, SR-Site, for the proposed repository at Forsmark. The specific objective is to get an understanding and an assessment of SKB’s quality assurance of the groundwater flow modelling in connection to SR-Site. The reliability of the results of the groundwater flow modelling depends inter alia...
Innehållstyp: Publikationer -
2015:01 Technical Note, Rock Mechanics - Thermal properties and thermal modelling of the rock in a repository of spent nuclear fuel at Forsmark – Main Review Phase
In preparation for the review of SKB's license application for a disposal of spent nuclear fuel, SSM has conducted a series of modelling studies related to the design, construction and long-term safety of a repository at Forsmark. Several of the presented modelling works are related to the thermal evolution of the repository with time. This report extracts the results from independent SSM...
Innehållstyp: Publikationer -
2017:18 FEM analysis of the mechanical integrity for the canister intended for storage of spent nuclear fuel with regard to copper creep ductility
Background For final storage of spent nuclear fuel it is suggested by the Swedish nuclear fuel and waste management company (SKB) to emplace the nuclear fuel into copper canisters which are surrounded by bentonite clay at approximately 500 meters’ depth into granitic rock. After emplacement of the canisters Bentonite swelling due to water saturation and hydrostatic pressure build up the...
Innehållstyp: Publikationer -
2016:37 PARTRIDGE project: Review and evaluation of the probabilistic fracture mechanics code PRO-LOCA
Background The Swedish Radiation Safety Authority (SSM) and the Swedish nuclear power plant owners have financed Inspecta Technology in Sweden to evaluate the PRO-LOCA code. It is a computer code, developed by Battelle in the USA, in which the leak- and rupture probabilities of piping in nuclear power plants are analysed. The pipe systems may contain the damage mechanisms fatigue and/or...
Innehållstyp: Publikationer -
2016:40 Analys av signalsvar från simulerade bindfel
Bakgrund Kvalificering av oförstörande provningssystem förutsätter att testblock som används vid praktiska demonstrationer innehåller tillverkade kvalificeringsdefek er med egenskaper som motsvarar de defekter som kan förekomma i aktuella anordningar. Bland annat behövs att dessa kvalificeringsdefek er ger relevanta signalsvar. De senaste åren har det...
Innehållstyp: Publikationer -
2015:50 Assessment of structures subject to concrete pathologies (ASCET)
Many Nuclear Power Plants around the world are at the moment approaching, or in, their Long Term Operation stage of their operational phase. In addition, several NPPs have recently been carrying out uprate and life extension projects and comprehensive maintenance work including the exchange of components important to safety, in order to extend their lifetime. As a result, ageing management...
Innehållstyp: Publikationer -
2015:27 APRI-8: Accident Phenomena of Risk Importance. En lägesrapport om forskningen inom området svåra haverier under åren 2012-2014
Kunskap om de fenomen som kan uppträda vid svåra haverier i en kärnkraftanläggning är en viktig förutsättning för att kunna förutse anläggningens beteende, för att kunna utforma rutiner och instruktioner för haverihantering, för beredskapsplaneringen samt för att få god kvalitet på haverianalyser och riskstudier. Sedan...
Innehållstyp: Publikationer -
2015:38 Evaluation of fatigue in austenitic stainless steel pipe components
Background Transferability of experimental results obtained for smooth test specimens under constant amplitude loading to realistic components subjected to variable amplitude loading is an important issue in the design against fatigue. There is a lack of experimental fatigue data for austenitic steel components and the present study is an important contribution to fill this gap. Objective The...
Innehållstyp: Publikationer