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Nuclide content and decay heat in ARIANE sample BM1 calculated using Serpent 2 : Impact from choice of nuclear data libraryFors, Staffan January 2022 (has links)
No description available.
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Modell för digitalisering av kurs : Reaktorfysik grund KSUGunnberg-Querat, Theodor, Krottler, Gustaf January 2023 (has links)
The nuclear industry is very complex which makes it so that the people working in the industry need ahigh level of understanding of how a nuclear power plant operates. This is why KSU(Kärnkraftsäkerhet och utbildning AB) is starting to look over their different courses and are trying tofind ways to improve them with new technology and a way to minimize the workload that theseeducations take, especially on the human resource side.The purpose of this paper is to create a method for digitization of a course for KSU.The method that was used started with a literature study, where relevant science papers were lookedinto and summarized and used for the formation of the course. Then the course was modularizedwhere the course goals got placed in modules and put in a flowchart to show in what ways you can gothrough the course. Thereafter a script was produced and a document with instructions that describesthe work and how it is to be put together which is called “metadokument”. The script contains all theinformation that a participant is expected to learn, together with the tool Lumi, which are combined ininteractive videos.The result shows a method that can be used to digitize courses that have been classroom lead beforeand the tools that can be used to do it.
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POLCA-T Neutron Kinetics Model BenchmarkingKotchoubey, Jurij January 2015 (has links)
The demand for computational tools that are capable to reliably predict the behavior of a nuclear reactor core in a variety of static and dynamic conditions does inevitably require a proper qualification of these tools for the intended purposes. One of the qualification methods is the verification of the code in question. Hereby, the correct implementation of the applied model as well as its flawless implementation in the code are scrutinized. The present work concerns with benchmarking as a substantial part of the verification of the three-dimensional, multigroup neutron kinetics model employed in the transient code POLCA-T. The benchmarking is done by solving some specified and widely used space-time kinetics benchmark problems and comparing the results to those of other, established and well-proven spatial kinetics codes. It is shown that the obtained results are accurate and consistent with corresponding solutions of other codes. In addition, a sensitivity analysis is carried out with the objective to study the sensitivity of the POLCA-T neutronics to variations in different numerical options. It is demonstrated that the model is numerically stable and provide reproducible results for a wide range of various numerical settings. Thus, the model is shown to be rather insensitive to significant variations in input, for example. The other consequence of this analysis is that, depending on the treated transient, the computing costs can be reduced by, for instance, employing larger time-steps during the time-integration process or using a reduced number of iterations. Based on the outcome of this study, one can finally conclude that the POLCA-T neutron kinetics is modeled and implemented correctly and thus, the model is fully capable to perform the assigned tasks.
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