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2017:36 Topical Peer Review 2017 Ageing Management Swedish National Assessment Report
Executive summary The European Union’s Nuclear Safety Directive 2014/87/EURATOM (NSD) requires the member states to undertake topical peer reviews (TPR) every 6 years with the first starting in 2017. The member states, acting through the European Nuclear Safety Regulators Group (ENSREG), have decided that the topic for the first topical peer review is ageing management. The Swedish Radiation...
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 -
2023:04 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 -
2017:16 Stress intensity factor solutions for circumferential cracks in cylindrical bars under axisymmetric loading and global bending
Background The case of a circumferential crack in a cylindrical bar has not been available in the ProSACC code. The need for such a geometry, especially considering nonlinear axisymmetric loading and global bending, has motivated the development of new stress intensity factor solutions, also known as K-solutions. These new K-solutions will be available in ISAAC, the successor to ProSACC.
Content type: Publications -
Nuclear power
Nuclear power currently represents approximately 30 per cent of Sweden’s national power supply. There are three nuclear power plants in the country, with a total of six reactors in operation. These NPPs are the Forsmark, Oskarshamn and Ringhals plants. The Forsmark NPP has three reactors in operation. The Oskarshamn NPP shut down two of its three reactors in 2017. The Ringhals NPP shut down...
Content type: Regular Pages -
2020:07 Fibre Clogging in Nuclear Power Plants
SSM perspective Background Emergency core cooling systems in boiling- and pressurized water reactors use strainers. Their purpose is to out foreign material suspended in the cooling water so this material does not reach the reactor. After the 1992 event at Barsebäck nuclear power plant when the strainers of the emergency cooling system was clogged due to fibers in the cooling water, all...
Content type: Publications -
2021:02 On Water Induced Sensitization of Ni (Fe,Cr) alloys towards Stress Corrosion Cracking in LWR Piping from 1st Principles Modelling
SSM perspective Background In Swedish Light Water Reactors (LWR), stress corrosion cracking of reactor components and welds occurs from time to time. As the nuclear power plants are ageing, it is essential to study and further understand the mechanism for environmentally induced sensitization. Natural cracking is a phenomenon that is difficult to predict and very hard to study since it occurs...
Content type: Publications -
2020:11 Competency based assessments of Nuclear Power Plant controlroom operators
Experiences of development and first operational methodological and technical demonstrator application...
Content type: Publications -
2020:12 Assessment of the QT-COOL coolant channel module against the PBF RIA 1-2 experiment
SSM perspective Background The fuel rod analysis program SCANAIR has been developed by IRSN (Institut de Radioprotection et de Sûreté Nucléaire) for analysis of reactivity initiated accidents (RIA) in light water reactors. The Swedish Radiation Safety Authority (SSM) has access to SCANAIR in exchange for annual contributions for its further development. This ensures a possibility...
Content type: Publications