Filtered generated 217 hits.
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2018:17 Assessment of structures subject to concrete pathologies (ASCET), phase 2
Background ASCET is an international research project initiated by WGIAGE1 OECD2 / NEA3. WGIAGE4 Concrete subgroup is a working group within the OECD / NEA whose task is to address issues concerning the maintenance of the integrity of concrete structures, proposals for general principles to optimally handle the challenges of integrity, especially with regard to aging of concrete structures.
Content type: Publications -
International radiation safety course in Stockholm gives participants practical knowledge
With radiation protection experts from all over the world and a focus on practical exercises and case studies, International Radiological Protection School (IRPS) gives professionals from over 20 different countries the opportunity for increased understanding of international radiation protection issues.
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 -
New wide call to strengthen research in nuclear power, waste management, radiation protection and nuclear non-proliferation
The Swedish Radiation Safety Authority is launching a wide research call covering four areas within radiation safety, including skills supply, nuclear non-proliferation, and the final disposal of nuclear waste. In total, the authority plans to allocate SEK 81 million for research during the period 2026–2031. International institutions are also eligible to apply for funding from one of the...
Content type: News -
2024:14 Residual stress distributions in nickel-based dissimilar metal pipe welds
SSM perspective This report concerns a study which has been conducted for the Swedish Radiation Safety Authority, SSM. The conclusions and viewpoints presented in the report are those of the author/authors and do not necessarily coincide with those of the SSM. Abstract It is common for nickel-base materials to be used as filler metals in the welding of dissimilar metal welds. Dissimilar metal...
Content type: Publications -
2025:01 Safety Concept Evaluation with Failure Tolerance Analysis
SSM perspective Background One of the most important design principles to achieve high safety function dependability is the use of redundancy to be single-fault tolerant. In turn, redundancies become effective by applying additional design principles such as physical and functional separation and diversity. License holders of nuclear power reactors must demonstrate that requirements are met,...
Content type: Publications -
IAEA IRRS-mission report to Sweden published
The International Atomic Energy Agency, IAEA, has reviewed Sweden’s framework for nuclear safety and radiation protection, the so-called IRRS review (Integrated Regulatory Review Service). The review is carried out every ten years by a group of international experts led by a team from the IAEA. Sweden’s second full-scope IRRS-review was carried out 14 – 25 November 2022. The report has now...
Content type: News -
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 -
2005:61 Review and Assessment of SCC Experiments with RPV Steels in Oskarshamn 2 and 3 (ABB Report SBR 99-020)
Although the extent of cracking was rather surprising for a bolt-loaded specimen, the average stress corrosion crack growth rate of 0.5 mm/year over the five-year testing period does not represent an immediate concern. The overwhelming part of crack growth can have occurred during a 20 day chloride transient during the third year of exposure because of a condenser leakage after an outage. The...
Content type: Publications -
1997:40 Aging of Electrical Components in Nuclear Power Plants
The purpose of the study reported in SKl Technical Report 93:39 was to evaluate qualification methods for application to components intended to be installed in the containment of nuclear power plants. The study included application of Arrhenius' criterion for thermal aging as well as methodologies for updating (curve-matching, ongoing qualification). This report reviews the results of...
Content type: Publications