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Din avgränsning ger 573 träffar.

• 2007:21 On tentative decommissioning cost analysis with specific authentic cost calculations with the application of the Omega code on a case linked to the Intermediate storage facility for spent fuel in Sweden

  The aim of this applied study has been to demonstrate how a cost calculation is done in a systematic way. The framework of the project has been limited to older nuclear installations in Sweden. Furthermore, it may be envisaged that the process of making regular estimates of all the parameters is crucial in preparatory phases of decommissioning and dismantling processes. A secondary aim of the...

  Innehållstyp: Publikationer

• 2007:02 Stakeholder involvement in Swedish nuclear waste management

  This report have attempted to show the development of stakeholder involvement in the siting of a final repository for Sweden’s spent nuclear fuel as resembling something other than a straightforward linear process of improvement and refinement. Stakeholder involvement has developed, over the past 15 years or so, in something more like a patchwork of different shapes and forms. Some of the...

  Innehållstyp: Publikationer

• 2007:32 Low pH Cements

  Concrete and cement are used in constructions as well as in conditioning of waste in repositories for radioactive waste. The development of low pH cements for use in geological repositories for radioactive waste stem from concerns over the potential for deleterious effects upon the host rock and other EBS materials (notably bentonite) under the hyperalkaline conditions (pH > 12) of cement...

  Innehållstyp: Publikationer

• 2007:29 Intercomparison of Cement Solid-Solution Models

  Many concepts for the geological storage of radioactive waste incorporate cement based materials, which act to provide a chemical barrier, impede groundwater flow or provide structural integrity of the underground structures. Thus, it is important to understand the long-term behaviour of these materials when modelling scenarios for the potential release and migration of radionuclides. In the...

  Innehållstyp: Publikationer

• 2016:02 Technical Note, An updated review of the creep ductility of copper including the effect of phosphorus

  Background The Swedish Radiation Safety Authority (SSM) reviews the Swedish Nuclear Fuel Company’s (SKB) applications under the Act on Nuclear Activities (SFS 1984:3) for the construction and operation of a reposi-tory for spent nuclear fuel and for an encapsulation facility. As part of the review, SSM commissions consultants to carry out work in order to obtain information on specific...

  Innehållstyp: Publikationer

• 2015:48 Technical Note, Supplementary review of SKB’s further RFI response

  Bakgrund Strålsäkerhetsmyndigheten (SSM) granskar Svensk Kärnbränslehantering AB:s (SKB) ansökningar enligt lagen (1984:3) om kärnteknisk verksamhet om uppförande, innehav och drift av ett slutförvar för använt kärnbränsle och av en inkapslingsanläggning. Som en del i granskningen ger SSM konsulter uppdrag för att inhämta...

  Innehållstyp: Publikationer

• 2016:05 Technical Note, Assessment of SKB TR-14-15 Assessment of SKB TR-14-15 “Possible influence from stray currents from high voltage DC power transmission on copper canisters”

  The general objective of the present project is to provide independent review comments for one area of SKB:s post closure safety analysis, SR-Site. With this in mind, the purpose of this report is to review SKB’s presentation on possible influence from stray currents from high voltage DC power transmission on a repository for nuclear fuel. Laust B Pedersen SSM English The general objective of...

  Innehållstyp: Publikationer

• 2015:40 Technical Note, Assessment of flow-related transport parameters used in the SR-Site safety case

  Joel E. Geier SSM English...

  Innehållstyp: Publikationer

• 2015:45 Technical Note, Parallel assessment of effects on non-human biota using RESRAD-BIOTA

  Karolina Stark SSM English...

  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