Visar 1337 sökträffar på publikationer
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2017:20 Assessment of inertia effects on transient clad-to-coolant heat transfer and coolant flow under reactivity initiated accidents
In this report, simple hydrodynamic models are used for studying the effects of coolant inertia on fuel-to-coolant heat transfer and coolant flow under reactivity initiated accidents in light water reactors. The objective is to assess if the inertia effects are important enough to warrant modification of QT-COOL, a coolant channel module for two-phase flow that has recently been implemented as...
Innehållstyp: Publikationer -
2017:19 Numerical simulations of headed anchors break in reinforced and non-reinforced concrete structures, Phase 2
Background In the design of anchorage equipment in concrete structures the beneficial effects of reinforcement are, in most cases, not considered. The American ASCI 349-06 code opens up for a more detailed analysis where the beneficial impact of reinforcement on anchor capacity can be taken into account. How this analysis can be done is, however, not explicitly described in the code. The...
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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...
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2017:17 Granskning och utvärdering av SKB:s redovisning av Fud-program 2016
Strålsäkerhetsmyndighetens yttrande Svensk Kärnbränslehantering AB (SKB) har lämnat in Fud-program 2016 till Strålsäkerhetsmyndigheten (SSM) för granskning och utvärdering enligt 12 § lagen 1984:3) om kärnteknisk verksamhet kärntekniklagen). SSM föreslår att regeringen beslutar att reaktorinnehavarna genom SKB:s redovisning...
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2017:16 Stress intensity factor solutions for circumferential cracks in cylindrical bars under axisymmetric loading and global bending
Background The case of a circumferential crack in a cylindrical bar has not been available in the ProSACC code. The need for such a geometry, especially considering nonlinear axisymmetric loading and global bending, has motivated the development of new stress intensity factor solutions, also known as K-solutions. These new K-solutions will be available in ISAAC, the successor to ProSACC.
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2017:15 Radionuclide release rates associated with bounding cases featuring relatively early canister failures in a spent fuel repository
Background In 2011 the Swedish Nuclear Fuel and Waste Management Co (SKB) submitted a license application for construction of a geological repository for spent nuclear fuel according to the KBS-3 method, comprising of copper canisters, bentonite buffer, backfill and surrounding crystalline bedrock. The post-closure safety assessment of the repository, SR-Site, has been reviewed by the Swedish...
Innehållstyp: Publikationer -
2017:14 Kriterier för klinisk revision av strålbehandling
Bakgrund I rådets direktiv 2013/59/Euratom definieras klinisk revision som systematisk utvärdering av medicinska radiologiska förfaranden i syfte att förbättra kvaliteten och resultaten i patientvården genom strukturerad översyn, varigenom medicinska radiologiska verksamheter, förfaranden och resultat granskas mot vedertagna normer för goda medicinska...
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2017:13 Monte Carlo patient-specific pre-treatment QA system for volumetric modulated arc therapy
Background The clinical use of volumetric modulated arc therapy (VMAT) has augmented rapidly since it became commercially available. As a result, the need for comprehensive quality assurance (QA) has increased. Current practices in Sweden normally compare the delivered dose with the planned dose based on measurements with different methods, for instance: portal dosimetry, point dose...
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2017:12 Computational assessment of LOCA simulation tests on high burnup fuel rods in Halden and Studsvik
Background Loss of Coolant Accidents (LOCA) are among the most demanding accidents that can happen in a Light Water Reactor (LWR). The lack of cooling and the drop in pressure impose large stresses on the nuclear fuel which would increase the risk of fuel rod damage and the subsequent release of active material. But LOCA is also an accident that the nuclear power plant is designed to...
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2017:11 Extended Common Load Model: A tool for dependent failure modelling in highly redundant structures
Background The treatment of dependent failures is one of the most controversial subjects in reliability and risk analyses. The difficulties are specially underlined in the case of highly redundant systems, when the number of redundant components or trains exceeds four. The Common Load Model (CLM), originally defined in the 70’ies, differs from other CCF models, as it relies on a specific...
Innehållstyp: Publikationer