Filtered generated 403 hits.
-
2012:29 Technical Note, Initial review of chemical and erosional processes within the buffer and backfill – Geochemical processes
De dokument i SR-Site som är relevanta till detta granskningsområde bedöms vara generellt i tillräckligt hög kvalitet för att utgöra underlagsmaterial för vidare granskning i huvudgranskningsfasen av SSM:s GLS- (granskning av långsiktig säkerhet) projekt. Behov av kompletterande information eller förtydliganden har dock identifierats inom...
Content type: Publications -
2012:26 Technical Note, Initial review of chemical and erosional processes within the buffer and backfill - Chemical erosion processes
The SR-Site documentation relevant to this review topic was found to be of sufficiently high quality overall to justify further consideration in the Main Review Phase of SSM’s PCS (Post-closure safety) project. Several specific topics for which complementary information and clarifications should be requested from SKB were also identified (Appendix 2). Specific review topics for consideration...
Content type: Publications -
2019:27 Effect of residual stress on ductile fracture at low primary loads – Numerical study
SSM perspective Background Present report is a continuation of earlier work reported in SSM2009:27 regarding an analysis strategy for fracture assessment of defects in ductile material and SSM2011:19 on the influence from residual stresses on crack initiation and ductile crack growth at high primary loads. The Swedish procedure for safety assessment of components with defects is documented in...
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 -
2019:16 SSM’s external experts’ reviews of SKB’s safety assessment SR-PSU
– consequence analysis and hydrogeological aspects Main review phase...
Content type: Publications -
98:35 Nuclear Fuel Assembly Assessment Project and Image Categorization
C. S. Lindsey (1), T. Lindblad (1), K. Waldemark (1), L. Hildningsson (2). (1) Royal Institute of Technology, Stockholm, Sweden. (2) Swedish Nuclear Power Inspectorate, Stockholm, Sweden. July 1998 SKI English...
Content type: Publications -
International peer review of repository application
The Swedish Radiation Safety Authority has performed a review of SKB’s (i.e. Svensk Kärnbränslehantering AB) application for construction of a repository for spent nuclear fuel, and recommends approval of this application, as stated in our pronouncement to the Government on 23 January 2018. A peer review has also been performed by OECD’s Nuclear Energy Agency (NEA) concerning the...
Content type: Regular Pages -
2018:19 Licensing of safety critical software for nuclear reactors
Background This report is the 7th revision of the report. The task force was formed in 1994 as a group of experts on safety critical software. The members come from regulatory authorities and/or their technical support organization. The report, without the SSM cover and this page, will be published by or available at the websites of the other participating organizations. Effect on SSM...
Content type: Publications -
1995:19 Non-destructive Assay of Spent BWR Fuel with High-resolution Gamma-ray Spectroscopy
A method, based on high-resolution gamma-ray spectroscopy, has been developed for verification of burnup, cooling time, power history and, to some extent, the initial enrichment of spent BWR fuel. It is shown that, provided that the power history is known and corrected for, bumup and cooling time can be verified with accuracies within 3% and 60 days, respectively, for cooling times up to about...
Content type: Publications -
2013:08 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, i.e. 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.
Content type: Publications