Filtered generated 401 hits.
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2013:06 The sixth round of implementation according to PARCOM recommendation 91/4 – Report from Sweden
According to the PARCOM Recommendation 91/4 contracting parties shall, in accordance with the guidelines annexed to this recommendation, every four years present a statement on progress made in applying best available technology (BAT) in order to minimise and, as appropriate, eliminate any pollution caused by radioactive discharges from all nuclear industries, including research reactors and...
Content type: Publications -
2012:02 Evaluation of activity build-up experiments
This project aims to understand how the water chemistry affects the activity build-up on surfaces in different systems in Swedish nuclear power plants, which in turn provides information on conditions required to reduce the radiation exposure to power plant staff. The study was done to obtain knowledge about water chemistry conditions preferred to minimize the activity build-up. A number of...
Content type: Publications -
2023:11 Study of degradation of spent fuel’s structural material and core components under long-term wet storage
SSM perspective Background Sweden is managing the spent nuclear fuel and core components from its commercial nuclear reactors with a national strategic plan. The fuel and core components are initially stored at the reactor site. After an on-site storage period to comply with transportation limits on decay heat and radiation, these materials are shipped to the Clab (Central Interim Storage...
Content type: Publications -
2023:14 Effect of gamma-irradiation on the redox states of the structural iron in bentonite clay
SSM perspective Background Bentonite clay is used as buffer and backfill material which form engineered barrier in the spent fuel repository. The buffer material surrounding the copper canister will be exposed to gamma and neutron radiations, especially during the first few hundred years after closure of the repository. The redox states of the structural iron in montmorillonite, the dominant...
Content type: Publications -
2023:13 TPR 2023 Fire Protection 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. The first topical peer review concerned Ageing management and started in 2017. The member states, acting through the European Nuclear Safety Regulators Group (ENSREG), decided that the topic for the second topical peer review...
Content type: Publications -
00:42 Study of Defect Characteristics Essential for NDT Testing Methods ET, UT and RT
This paper presents results from a literature review of defect characteristics essential for non-destructive testing (NDT). Most of the major NDT methods are included in the study - ultrasonic testing (UT), radiography (RT) and eddy current testing (ET). The study was performed by means of searching in scientific databases, technical journals, conference proceedings etc. Mainly, the following...
Content type: Publications -
2002:04 Qualification of Electrical Components in Nuclear Power Plants. Management of Ageing
The work was finished and reported in Swedish in a limited publication 2000, Ingemansson Rapport H-14061-r-I. As the performed work was regarded to be of more general interest it is published again as a research report by the Swedish Nuclear Power Inspectorate. To be used in the international cooperation in nuclear safety it was also translated into English by the inspectorate, which is this...
Content type: Publications -
2009:12 Evaluating safety-critical organizations – emphasis on the nuclear industry
The regulator identified a few years ago a need for a better understanding of and a deeper knowledge on methods for evaluating safety critical organisations. There is a need for solid assessment methods in the process of management of organisational changes as well as in continuously performed assessment of organisations such as nuclear power plants. A considerable body of literature exists...
Content type: Publications -
2007:05 Development of an Input Model to MELCOR 1.8.5 for Oskarshamn 3 BWR
200 Lars Nilsson SKI English...
Content type: Publications -
2021:04 Calibration of models for cladding tube high-temperature creep and rupture in the FRAPTRAN-QT-1.5 program
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