Filtered generated 373 hits.
-
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...
Content type: Publications -
2016:02 Technical Note, An updated review of the creep ductility of copper including the effect of phosphorus
Kjell Pettersson SSM English...
Content type: Publications -
2008:05 International Expert Review of SR-Can: Safety Assessment Methodology - External review contribution in support of SSI's and SKI's review of SR-Can
In 2006, SKB published a safety assessment (SR-Can) as part of its work to support a licence application for the construction of a final repository for spent nuclear fuel. The report represented the culmination of work conducted by SKB over several years, focusing on the goal of making the licence application in late 2009. Results from the SR-Can project have been documented in several...
Content type: Publications -
1995:15 Determination of the Neutron and Photon Dose Equivalent at Work Places in Nuclear Facilities of Sweden
The radiation fields in nuclear power plants consist of a mixture of photons and neutrons of various energies. A detector is usually constructed to respond to one type of radiation only and is usually useful in a limited energy range . .This is especially so for neutrons. Accurate descriptions of the radiation envirorunent are therefore very complicated to obtain. During the last decade great...
Content type: Publications -
1986:12 Chernobyl - its impact on Sweden
In case of a radiological emergency in Sweden, the Swedish National Institute of Radiation Protection (SSI) has the responsibility of organ1z1ng a special task force with experts both from SSI and from other authorities. Reports of increased radiation l evels reached SSI around 10 am on April 28, 1986, and the task force convened at 1030 am. A large number of measurements were made all over...
Content type: Publications -
2021:10 Establishment and use of attention values in environmental fatigue assessments
SSM perspective Background As Swedish NPPs reach their original technical design life, re-assessment of the fatigue life of structural components is needed for safe long term operation (LTO). In these re-assessments one must consider that new knowledge has shown that environmental effects on fatigue life must be considered. One common method to verify the fatigue life of structural components...
Content type: Publications -
2019:01 Research within technical safeguard at Uppsala university during 2016-20
Summary Uppsala University has since January 2016 undertaken an extensive research programme in technical nuclear safeguards within the framework of contract SSM2016-661, including in total 3 PhD students and 7 senior researchers. This report marks the final reporting covered by this contract. The executed research covers the following projects; (1) Methodologies for safeguards assessment of...
Content type: Publications -
2021:09 Mechanisms important for material modelling in weld residual stress analysis
SSM perspective Background The prediction of weld residual stresses (WRS) is very complex as many mechanisms and phenomena influence the development of WRS during welding. For accurate prediction, the constitutive material models used are essential and must be able to describe the material response of the weldment constituents. For example, selection of a material model should only depend on...
Content type: Publications -
2024:17 Atomistic studies on the adsorption and desorption of radionuclides on fuel crud and system surfaces in Light Water Reactors
SSM perspective Background Radiation safety is of particular concern during power plant maintenance. Radionuclides produced by the neutron bombardment in the core during operation may accumulate on system surfaces such as the filter system or piping and contribute to the radiation field. Some ions that are prone to neutron capture often become trapped in the deposits on the fuel cladding...
Content type: Publications -
2023:14 Effect of gamma-irradiation on the redox states of the structural iron in bentonite clay
SSM perspective Background Bentonite clay is used as buffer and backfill material which form engineered barrier in the spent fuel repository. The buffer material surrounding the copper canister will be exposed to gamma and neutron radiations, especially during the first few hundred years after closure of the repository. The redox states of the structural iron in montmorillonite, the dominant...
Content type: Publications