Filtered generated 57 hits.
-
2016:31 Measures and method characteristics for early evaluation of safe operation in nuclear power plant control room systems
1655 kB...
Content type: Documents -
2016:13 Spännarmerade betongkonstruktioner vid kärntekniska anläggningar
2789 kB...
Content type: Documents -
2016:18 En standardiserad svensk nomenklatur för strålbehandling
1578 kB...
Content type: Documents -
2016:15 Recent Research on EMF and Health Risk, Eleventh report from SSM’s Scientific Council on Electromagnetic Fields, 2016
1778 kB...
Content type: Documents -
2016:14 Radiological examinations of children: a study of method options
1328 kB...
Content type: Documents -
2016:23 Technical Note, Modelling of the thermal evolution of the KBS-3 repository at Forsmark and associated induced seismic activity
Main Review Phase Introduction 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 the KBS-3 repository 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...
Content type: Publications -
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 -
2016:09 SSM’s external experts’ reviews of SKB’s safety assessment SR-PSU – radionuclide transport, dose assessment, and safety analysis methodology
Initial review phase SSM English Initial review phase...
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 -
2016:25 Licensing of safety critical software for nuclear reactors
It is widely accepted that the assessment of software cannot be limited to verification and testing of the end product, ie the computer code. Other factors such as the quality of the processes and methods for specifying, designing and coding have an important impact on the implementation. Existing standards provide limited guidance on the regulatory and safety assessment of these factors. An...
Content type: Publications