Din avgränsning ger 571 träffar.
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2013:16 Technical Note, Assessment of PWR fuel depletion and of neutron multiplication factors for intact PWR fuel copper canisters – main review phase
SKB (Svensk Kärnbränslehantering AB) in 2011 applied to the Swedish government for approval of a proposed solution for disposal of used fuel from Swedish nuclear power reactors and some relatively minor quantities of other fissile material. This Technical Note contains results of a recent review of the SKB methods used to determine the influence of reactor depletion on keff of intact...
Innehållstyp: Publikationer -
1999:51 Kostnadsberäkning av diupförvaringav det använda kärnbränslet
Enligt finansieringslagen skall kärnkraftföretagen, i praktiken Svensk Kärnbränslehantering AB (SKB), årligen till Statens kärnkraftinspektion (SKI) lämna en beräkning över kostnaderna för att omhänderta det använda kärnbränslet och för avvecklingen och rivningen av kärnkraftverken. Efter att SKI granskat och värderat...
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 -
2011:31 Allocation of Decommissioning and Waste Liabilities
A crucial task for the present generations is to ensure that environmental liabilities are identified sufficiently well so that it may be possible to accumulate the corresponding necessary financial assets in the Swedish Nuclear Waste Fund. Adequate funding will provide forthcoming generation’s with the financial means to decommission and dismantle older nuclear facilities that are part of...
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 -
2016:25 Licensing of safety critical software for nuclear reactors
– Common position of international nuclear regulators and authorised technical support organisations – Revision 2015...
Innehållstyp: Publikationer -
2016:35 Säkerhetsvärdering mot plastisk kollaps vid skadetålighetsanalyser
Bakgrund Proceduren som används för brottmekanisk analys av defekter och inspektionsintervall för komponenter i svenska kärntekniska anläggningar utgår från den brittiska R6-metoden men är vidareutvecklad för att ha ett säkerhetsvärderingssystem som är kompatibelt med säkerhetskraven som uttrycks i den amerikanska tryckkärlsstandarden...
Innehållstyp: Publikationer -
2016:29 Evaluation of the Swedish participation in the Halden Reactor Project 2006–2014
This is a report on the evaluation of the Swedish participation in the Halden Reactor Project 2006-2014. The study has consisted in evaluating the types and extent of added value from the Swedish participation in the Halden Reactor Project, and to determine what additional added value the participation could supply for the Swedish authority. It can be concluded from the study that the impacts...
Innehållstyp: Publikationer -
2016:39 Recommended residual stress profiles for stainless steel pipe welds
Background The Swedish Radiation Safety Authority (SSM) and the Swedish nuclear power plant owners have financed Inspecta Technology in Sweden to analyze stainless steel pipe welds to obtain good estimations of weld residual stress (WRS) distributions. Detailed knowledge of the residual stress field in different types of welds is important since they can have substantial influence on...
Innehållstyp: Publikationer -
2016:27 Validation of fatigue fracture mechanics approaches
Background In a previous study (SSM research report 2015:38) fatigue experiments were performed on welded austenitic stainless steel piping components. The fatigue experiments offer an opportunity to evaluate fatigue flaw tolerance assessments used in industry, which are based on the fracture mechanical approach implemented in ProSACC. Objective The present study aims to validate the used...
Innehållstyp: Publikationer