Filtered generated 278 hits.
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2017:15 Radionuclide release rates associated with bounding cases featuring relatively early canister failures in a spent fuel repository
Background In 2011 the Swedish Nuclear Fuel and Waste Management Co (SKB) submitted a license application for construction of a geological repository for spent nuclear fuel according to the KBS-3 method, comprising of copper canisters, bentonite buffer, backfill and surrounding crystalline bedrock. The post-closure safety assessment of the repository, SR-Site, has been reviewed by the Swedish...
Content type: Publications -
2019:06 The Changing Landscape of Non-proliferation and the EU
Background Maintaining competence and knowledge within the nuclear non-proliferation area is a necessity for Sweden to keep its international commitments of peaceful use of all nuclear material. As part of this work the Swedish Radiation Safety Authority (SSM) made a call for research proposals related to Non-Proliferation for projects focused on the interplay between national and...
Content type: Publications -
2019:08 Recent Research on EMF and Health Risk, Thirteenth report from SSM’s Scientific Council on Electromagnetic Fields, 2018
SSM perspective Background The Swedish Radiation Safety Authority’s (SSM) Scientific Council on Electromagnetic Fields monitors current research on potential health risks with a correlation to exposure to electromagnetic fields and provides the Authority with advice on assessing possible health risks. The Council gives guidance when the Authority must give an opinion on policy matters when...
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 -
2019:27 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 -
2014:04 Global Non-proliferation ‘Clubs’ vs. the NPT
The study analyses the relationship between the Nuclear Non-Proliferation Treaty, NPT and various initiatives and institutions (‘clubs’) based outside the NPT framework, which aims to improve and strengthen the Treaty. The study identifies conflicts and possible synergies and proposes options for developing and improving the interaction between the NPT and ‘clubs’ in order to increase the...
Content type: Publications -
2011:02 The Back-End of the Nuclear Fuel Cycle in Sweden, Considerations for safeguards and data handling
The report is a compilation report consisting of three papers. A safeguards approach for the planned encapsulation facility and the operating final repository is presented in paper 1. Special considerations concerning safeguards for the final disposal process have been discussed and incorporated into the approach. Paper 2 defines the spent fuel data that must be secured, for safeguards...
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 -
2016:27 Validation of fatigue fracture mechanics approaches
Background In a previous study (SSM research report 2015:38) fatigue experiments were performed on welded austenitic stainless steel piping components. The fatigue experiments offer an opportunity to evaluate fatigue flaw tolerance assessments used in industry, which are based on the fracture mechanical approach implemented in ProSACC. Objective The present study aims to validate the used...
Content type: Publications -
2016:29 Evaluation of the Swedish participation in the Halden Reactor Project 2006–2014
This is a report on the evaluation of the Swedish participation in the Halden Reactor Project 2006-2014. The study has consisted in evaluating the types and extent of added value from the Swedish participation in the Halden Reactor Project, and to determine what additional added value the participation could supply for the Swedish authority. It can be concluded from the study that the impacts...
Content type: Publications