Din avgränsning ger 336 träffar.
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Kärnkraftsindustrins forsknings- och utvecklingsprogram för avfallshantering kan godkännas
Kärnkraftsindustrins forsknings- och utvecklingsprogram för att ta hand om avfallet från kärnkraftverken lever upp till lagens krav. Det konstaterar Strålsäkerhetsmyndigheten i ett yttrande till regeringen. Det är därefter regeringen som fattar beslut om programmet kan godkännas.
Innehållstyp: Nyheter -
IAEA har fastställt IRRS-granskning
FN:s atomenergiorgan IAEA har för andra gången granskat hur väl Sverige lever upp till internationella riktlinjer inom kärnsäkerhet och strålskydd, den så kallade IRRS-granskningen (Integrated Regulatory Review Service). Granskningen görs var tionde år av en grupp internationella experter under ledning av IAEA. Den senaste genomfördes 14 – 25 november...
Innehållstyp: Nyheter -
Nu kan du anmäla dig till Nationella strålsäkerhets- och forskningsdagarna 26–27 oktober 2023
Strålsäkerhetsmyndigheten bjuder in till Nationella strålsäkerhets- och forskningsdagar 26–27 oktober 2023 i Stockholm.
Innehållstyp: Nyheter -
Internationell strålsäkerhetsutbildning i Stockholm ger deltagarna praktisk kunskap
Med strålskyddsexperter från hela världen och fokus på praktiska övningar och fallstudier ska International Radiological Protection School (IRPS) ge yrkesverksamma från över 20 olika länder möjlighet till fördjupning och ökad förståelse för internationella strålskyddsfrågor.
Innehållstyp: Nyheter -
2019:23 Participation in the European Committee for Standardization's workshop regarding civil structures
SSM perspective Background During the period 2014-2018, a CEN1 workshop (Phase 2 Prospective Group 3 civil works) have been carried out. The aim of the workshop is to provide a base founded on the French standard in order to be able to establish a possible future European standard for the design of civil structures at nuclear power plants. The workshop has identied which additional...
Innehållstyp: Publikationer -
2019:20 Assessment of structures subject to concrete pathologies (ASCET), phase 3
SSM perspective Background ASCET is an international research project initiated by WGIAGE1 OECD2 / NEA3. WGIAGE Concrete subgroup is a working group within the OECD / NEA whose task is to address issues concerning the maintenance of the integrity of concrete structures, proposals for general principles to optimally handle the challenges of integrity, especially with regard to ageing of...
Innehållstyp: Publikationer -
2019:15 3D Thermo-Mechanical Coupled Modelling of Thermo-Seismic Response of a Fractured Rock Mass related to the Final Disposal of Spent Nuclear Fuel and Nuclear Waste in Hard Rock
SSM perspective Background When assessing the long-term safety of a repository for spent nuclear fuel it is important to consider future earthquakes. Previous studies by Yoon et al. (2014, SSM Report 2014:59) and (2016, SSM Report 2016:23) investigated the fracture responses due to heat and earthquakes at major deformation zones using a 2D thermo-mechanical coupled model that uses a Particle...
Innehållstyp: Publikationer -
2006:36 Mechanical Integrity of Canisters Using a Fracture Mechanics Approach
This report presents the methods and results of a research project for Swedish Nuclear Power Inspectorate (SKI) about numerical modeling of mechanical integrity of cast-iron canisters for the final disposal of spent nuclear fuel in Sweden, using combined boundary element (BEM) and finite element (FEM) methods The objectives of the project are: 1) to investigate the possibility of initiation...
Innehållstyp: Publikationer -
2007:17 Spent Fuel Dissolution and Source Term Modelling in Safety Assessment
SKI is preparing to review the license applications being developed by the Swedish Nuclear Fuel and Waste Management Company (SKB) for a final repository for the geological disposal of spent nuclear fuel (SFL-2) in the year 2009. As part of its preparation, SKI is conducting a series of technical workshops on key aspects of the Engineered Barrier System (EBS) and spent fuel. This workshop...
Innehållstyp: Publikationer -
2007:12 Development of a constitutive model for the plastic deformation and creep of copper and its use in the estimate of the creep life of the copper canister
The copper-iron canister for disposal of nuclear waste in the Swedish Programme has a design life exceeding 100,000 years. Whilst the operating temperature and operating stress are modest, the very long design life does require that the likely creep performance of the canister should be investigated. Many studies have been carried out by SKB but these have all involved very short duration...
Innehållstyp: Publikationer