Din avgränsning ger 268 träffar.
-
2007:10 DECOVALEX-THMC - Task D
Inspectorate, with participation of about 10 international organizations. The name DECOVALEX stands for DEvelopment of COupled models and their VALidation against Experiments. The general goal of this project ... coupled processes in geologic formations in support of the performance assessment for underground storage of radioactive waste. Three multi-year project stages of DECOVALEX have been completed in the past decade...
Innehållstyp: Publikationer -
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 ... resist a specified earthquake. For the older reactors no corresponding analyses or designs have been made initially. Their general design is robust.and was considered to provide enough safety with regard...
Innehållstyp: Publikationer -
SSM Report 2008:01 A combined deterministic and probabilistic procedure for safety assessment of components with cracks – Handbook
further development of a previously developed procedure/handbook (SKI Report 99:49) for assessment of detected cracks and tolerance for defect analysis. During the operative use of the handbook it was ... needs to update the deterministic part of the procedure and to introduce a new probabilistic flaw evaluation procedure. Another identified need was a better description of the theoretical basis to the computer...
Innehållstyp: Publikationer -
2010:45 Evaluation of models for cyclic plastic deformation – A literature study
Analysis of nuclear components subjected to cyclic plastic deformation is normally based on the American standard ASME III. With the focus to improve the modeling of the stress-strain response under non-monotonic ... loading, several models for the analysis of cyclic plastic deformation have been developed in recent years. However, experience shows that the analysis and evaluation of plastic cycling and its impact on component...
Innehållstyp: Publikationer -
1997:40 Aging of Electrical Components in Nuclear Power Plants
The purpose of the study reported in SKl Technical Report 93:39 was to evaluate qualification methods for application to components intended to be installed in the containment of nuclear power plants. ... study included application of Arrhenius' criterion for thermal aging as well as methodologies for updating (curve-matching, ongoing qualification). This report reviews the results of complementary tests, including...
Innehållstyp: Publikationer -
2019:03 Evaluation of the hydrodynamic model in PARET/ANL
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 ... its further development. This ensures a possibility for SSM to do own analysis of fuel rods in reactivity initiated accidents. The development and administration of the program is done by Quantum Technologies...
Innehållstyp: Publikationer -
2023:11 Study of degradation of spent fuel’s structural material and core components under long-term wet storage
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 ... is located in Oskarshamn, Sweden. The Clab facility operates several linked underground storage pools which are expected to have a storage capacity of 11,000 tons. Figure 1 is a photo of one of the underground...
Innehållstyp: Publikationer -
2009:12 Evaluating safety-critical organizations – emphasis on the nuclear industry
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 ... 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 concerning assessment...
Innehållstyp: Publikationer -
2016:39 Recommended residual stress profiles for stainless steel pipe welds
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 ... have been performed by using 2-dimensinal finite element technique for a set of cases covering most stainless steel pipe welds in Swedish nuclear power plants, together with sensitivity studies with respect...
Innehållstyp: Publikationer -
2022:03 Effect of Neutron Irradiation on the Oxidation and Corrosion of Austenitic Stainless Steels
pressure vessel internal components of austenitic stainless steel located close to the core are subject to a high neutron flux. Irradiation by fast neutrons induces changes in the material that affect microstructure ... the water environment through radiolysis, which creates oxidizing species in the water that could affect oxidation and corrosion of the material. Flux thimble tubes that had been in service in Ringhals...
Innehållstyp: Publikationer