Filtered generated 399 hits.
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2017:05 Robust structural verification of pressurized nuclear components subjected to ratcheting, part two – stress-strain curves for cyclic elastoplastic analysis.
Background Pressurized components in nuclear applications that are subjected to cyclic loading may exhibit progressive deformation, so called structural ratcheting. If the component is made out of a material that are deformation hardening, it may also exhibit material ratcheting. The combined effects of structural- and material ratcheting are not taken into account in the methods and material...
Content type: Publications -
2017:12 Computational assessment of LOCA simulation tests on high burnup fuel rods in Halden and Studsvik
Background Loss of Coolant Accidents (LOCA) are among the most demanding accidents that can happen in a Light Water Reactor (LWR). The lack of cooling and the drop in pressure impose large stresses on the nuclear fuel which would increase the risk of fuel rod damage and the subsequent release of active material. But LOCA is also an accident that the nuclear power plant is designed to...
Content type: Publications -
2017:32 COMRAD – Comprehensive investigation of the performance of computed and digital radiography
Background Within the industry, there has long been a need to replace the traditional X-ray film and its handling. These both for economic and environmental considerations. Both computed radiography and digital radiography offer many advantages over the traditional use of x-ray with film. However, the transition from film-based radiography requires in-depth knowledge of the relationship...
Content type: Publications -
2023:07 General data in accordance with the requirements in Article 37 of the Euratom Treaty
Increased storage of spent nuclear fuel at Clab in Sweden...
Content type: Publications -
2024:10 Computational analysis of high-burnup fuel rod behaviour in PWR large-break LOCA
SSM perspective Background Quantum Technologies AB (QT) has for many years developed computational models for the thermomechanical behaviour of nuclear fuel in events such as LOCA and RIA. The research projects have been based on evaluations of tests on nuclear fuel in Halden Reactor Project (HRP) and Studsvik Cladding Integrity Project (SCIP). The models developed by QT enable analyses and...
Content type: Publications -
2023:04 Kingdom of Sweden ARTEMIS Self-assessment Report 2023
Foreword In January 2018, the Swedish Radiation Safety Authority, SSM, submitted a request to the IAEA on behalf of the Swedish Government for international peer reviews to be conducted of the Swedish national frameworks for nuclear safety regulation (IRRS) and the safe management of spent fuel and radioactive waste (ARTEMIS). In dialogue with the IAEA, and in support of the then Swedish...
Content type: Publications -
New Report: Sweden's Self-Evaluation on Meeting Joint Convention Obligations
Transparency and public participation in the final waste disposal programme, progress of Sweden's nuclear waste management program, and preparations for licensing of new nuclear reactors are some of the areas highlighted in the report presenting Sweden's self-assesment under the Joint Convention.
Content type: News -
Swedish Radiation Safety Authority submits proposals for existing and future nuclear power
The Swedish Radiation Safety Authority (SSM) has today finalized the assignment from the government to investigate how laws, regulations and other measures can be developed for existing and future nuclear power.
Content type: News -
Sweden ready for upcoming IAEA IRRS-review
The Swedish Radiation Safety Authority has completed its reporting in preparation for the international peer-review on how Sweden complies with international guidelines on nuclear safety and radiation protection. The review is carried out by the IAEA and international experts and takes place in Sweden from 14 to 25 November 2022.
Content type: News