Filtered generated 215 hits.
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2015:07 TEM-lamella lift-out from the crack tip region of Alloy 600 for high resolution electron microscopy examination
This report contributes to the development of a method for high-quality TEM lamella preparation from crack tip regions of nuclear materials. A standard compact tension (CT) specimen of Alloy 600 previously tested for stress corrosion crack growth in simulated PWR primary water was used to demonstrate the benefit of the proposed method. This report describes the procedure for cutting the CT...
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 -
1992:3 Characterization of seismic ground motions for probabilistic safety analyses of nuclear facilities in Sweden. SUMMARY REPORT
In Scandinavia seismic activity is generally low. Only a few incidents have been registered in historic time, which might have damaged an industrial plant of today. The risk of a nuclear accident in Sweden, caused by an earthquake, may thus be considered to be low. The two latest reactors Forsmark 3 and Oskarshamn 3 have been analysed and designed to resist a specified earthquake. For the...
Content type: Publications -
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 -
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 -
2008:07 Modelling of long term geochemical evolution and study of mechanical perturbation of bentonite buffer of a KBS-3 repository
PART I: The Swedish Nuclear Fuel and Waste Management Co. (SKB) has recently completed a safety assessment project named SR-Can, related to the KBS-3 disposal concept. In this concept, the waste packages are surrounded by a buffer made of either MX-80 or Deponit CA-N bentonite. Interactions between the buffer and groundwater may modify the buffer composition and thus its containment...
Content type: Publications -
2008:09 The Generalised Ecosystem Modelling Approach in radiological assessment
An independent modelling capability is required by SSI in order to evaluate dose assessments carried out in Sweden by, amongst others, SKB. The main focus is the evaluation of the long-term radiological safety of radioactive waste repositories for both spent fuel and low-level radioactive waste. To meet the requirement for an independent modelling tool for use in biosphere dose assessments,...
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 -
2021:20 Effects of additives on UO2 fuel behavior: expanded edition
SSM perspective Background The Swedish Radiation Safety Authority (SSM) follows the development of nuclear fuel closely. Fuel with additives like chromia and gadolinia is used in Swedish reactors and fuel with even better thermal and mechanical properties is under development. This project is an in-depth study of data and models regarding the impact of additives on the properties of uranium...
Content type: Publications -
2024:18 Modelling Environmental Sensitization of Chromia Forming Nickel Base Alloys Toward Stress Corrosion Cracking in Light Water Reactors by Atomistic Simulations
SSM perspective Background Stress corrosion cracking (SCC) in load bearing structures has been a longstanding issue both in pressurized and boiling water reactors. The specific environment in nuclear power applications consists of high temperatures and pressures that together with the effects of the radiation field on the coolant composition provide tough conditions for the materials used in...
Content type: Publications