Filtered generated 375 hits.
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2011:30 A fatigue analysis including environmental effects for a pipe system in a Swedish BWR
The effect of the environment on fatigue design has been the subject of intense study in USA, Japan and elsewhere. Several reports indicate a potentially large influence of the environment, leading to the proposal of entirely new analysis procedures. SSM has in an earlier project sponsored research to evaluate the technical basis for these proposals, see SSM Research Report 2011:04. In the...
Content type: Publications -
2013:04 Research and Development Program in Reactor Diagnostics and Monitoring with Neutron Noise Methods, Stage 18
The program executed in Stage 18 consists of the following three parts: Application of CoreSim with a two-dimensional model of vibrating fuel assemblies, for the calculation of ex-core detector noise throughout a fuel cycle; An investigation of the neutron noise, induced by propagating perturbations, in various thermal and fast reactor systems, in two-group theory; A consistent derivation of...
Content type: Publications -
2014:20 An evaluation of high-temperature creep of zirconium alloys: data versus models
In this report Dr Massih presents correlations for creep in different phases of zirconium alloys and also presents a general solution to the difficulty of accurately describing the material properties in phase transition for several zirconium alloys. Based upon superplasticity relations, models are adapted to fit with experimental data for materials in transition regions. The creep models are...
Content type: Publications -
2016:25 Licensing of safety critical software for nuclear reactors
It is widely accepted that the assessment of software cannot be limited to verification and testing of the end product, ie the computer code. Other factors such as the quality of the processes and methods for specifying, designing and coding have an important impact on the implementation. Existing standards provide limited guidance on the regulatory and safety assessment of these factors. An...
Content type: Publications -
2016:29 Evaluation of the Swedish participation in the Halden Reactor Project 2006–2014
This is a report on the evaluation of the Swedish participation in the Halden Reactor Project 2006-2014. The study has consisted in evaluating the types and extent of added value from the Swedish participation in the Halden Reactor Project, and to determine what additional added value the participation could supply for the Swedish authority. It can be concluded from the study that the impacts...
Content type: Publications -
2016:39 Recommended residual stress profiles for stainless steel pipe welds
Background The Swedish Radiation Safety Authority (SSM) and the Swedish nuclear power plant owners have financed Inspecta Technology in Sweden to analyze stainless steel pipe welds to obtain good estimations of weld residual stress (WRS) distributions. Detailed knowledge of the residual stress field in different types of welds is important since they can have substantial influence on...
Content type: Publications -
2016:27 Validation of fatigue fracture mechanics approaches
Background In a previous study (SSM research report 2015:38) fatigue experiments were performed on welded austenitic stainless steel piping components. The fatigue experiments offer an opportunity to evaluate fatigue flaw tolerance assessments used in industry, which are based on the fracture mechanical approach implemented in ProSACC. Objective The present study aims to validate the used...
Content type: Publications -
2015:11 Investigation of the Distribution of Phosphorus in Copper
Two copper alloys containing different amounts of phosphorus, 6 and 80 wtppm, respectively, have been investigated. The matrix of both alloys was analysed using atom probe tomography (APT). The matrix P concentration in the 80 wtppm P mate- rial was about the same as the bulk concentration and it was therefore concluded that the majority of the P atoms resides in the matrix. Grain boundaries...
Content type: Publications -
2014:56 Seismic design and analysis of safety-related nuclear structures in Sweden
The report presents the historical development of the seismic design for the U.S., France and Sweden with special focus on issues related to severe earthquakes beyond the design basis as well as important aspects concerning the design basis ground motions for the Swedish nuclear facilities. The report provides recommendations on a revised model for seismic hazard assessments, on minimum...
Content type: Publications -
2015:43 Robust structural verification of pressurized nuclear components subjected to ratcheting
Background Pressurized components in nuclear applications that are subjected to cyclic loading may exhibit progressive deformation, so called structural ratcheting. If the component is made out of a material that are deformation hardening, it may also exhibit material ratcheting. The combined effects of structural- and material ratcheting are not taken into account in the methods and material...
Content type: Publications