Filtered generated 280 hits.
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96:51 The Flooding Incident at the Ågesta Pressurized Heavy Water Nuclear Power Plant
This report is a Master's thesis in Nuclear Reactor Engineering to be submitted to the SKi (Swedish Nuclear Power Inspectorate). The work has been performed at the Division of Nuclear Power Safety, KTH,Stockholm. It is an independent investigation of the consequences of the flooding incident at the Agesta HPWR, in Stockholm, Sweden, which occurred on the 1st of May 1969. The issue was raised...
Content type: Publications -
1994:15 Aging Degradation of Concrete Structures in Nuclear Power Plants
This report on the aging-related degradation of concrete structures in nuclear power plants was prepared by Battelle Seattle Research Center for the Swedish Nuclear Power Inspectorate (SKI). The purpose of this report is to provide an understanding of how concrete structures in nuclear power plants degrade over time. This report is based on the studies of concrete aging commissioned by the...
Content type: Publications -
2020:04 Recent Research on EMF and Health Risk, Fourteenth report from SSM’s Scientific Council on Electromagnetic Fields, 2019
SSM perspective Background The Swedish Radiation Safety Authority’s (SSM) Scientific Council on electromagnetic Fields monitors current research on potential health risks in relation 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 -
2020:01 Sulphide-induced stress corrosion cracking and hydrogen absorption incopper exposed to sulphide and chloride containing deoxygenated water at 90°C
SSM perspective Background The concept that the Swedish nuclear power industry plans to utilise for the final disposal spent nuclear fuel is called KBS-3 method, which is based on three different barriers to prevent spreading of radioactive substances: copper canisters, bentonite buffers and the surrounding Swedish bedrock. In the current KBS-3 design, the spent nuclear fuel will be placed in...
Content type: Publications -
2020:13 Core data Research at Uppsala University
SSM perspective Background This project is to support a research group at Uppsala University in the research field of nuclear data for applications. Nuclear data research is about measuring microscopic cross-sections and developing theoretical nuclear models to create evaluated nuclear data libraries. These nuclear data libraries are used in different applications such as, nuclear technology,...
Content type: Publications -
2020:02 Models for axial gas flow and mixing in LWR fuel rods
SSM perspective Background Fission gases inside a fuel rod plays an important role in the behaviour of the fuel, both during normal operation and during events and accidents. Fission gases are released from inside the fuel pellets to the gap between the pellet and the cladding tube and then flow to the plenum volume at the top of the fuel rod. In high burnup fuel, this axial flow to the...
Content type: Publications -
2021:08 Recent Research on EMF and Health Risk, ifteenth report from SSM’s Scientific Council on Electromagnetic Fields, 2020
SSM perspective Background The Swedish Radiation Safety Authority’s (SSM) Scientifc Council on Electromagnetic Fields monitors current research on potential health risks in relation 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 scientific...
Content type: Publications -
2021:28 Analysis of Radon Levels in Swedish Dwellings and Workplaces
SSM perspective Background Exposure to radon is considered the second most important cause of lung cancer next to smoking and is estimated to account for about 500 lung cancer cases per year in Sweden. For this reason, it is important to lower radon concentrations in indoor air, particularly where levels exceed the reference level 200 Bq/m³. In order to be able to update calculations on number...
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 -
2020:16 Estimates ofJ-integral and COD for circumferential through wall cracks under global bending including the effect of pipe end restraint
SSM perspective Background Leak-before-break (LBB) piping assessments have shown that piping systems can withstand long through-wall cracks before pipe rupture is expected. This is somewhat because pipe ends are restrained. In LBB assessments analyses are often performed for a pipe segment uncoupled from the piping system, as pipe ends are assumed unrestrained. This assumption is conservative...
Content type: Publications