The surtax in Sweden, which exclusively applies for nuclear power plants, in conjunction with low electricity prices, has forced Swedish nuclear power plants to minimize their expenses. At Oskarshamn power plant, estimation of cost, associated with low-level nuclear waste management has been conducted several years ago, but with lacking knowledge about how the calculations were performed. Therefore, the purpose of this project was to establish an independent cost estimation for compactible and non-compactible, low level and medium level nuclear waste. Cost estimates for free released low-level nuclear waste was also performed. By analyzing average economic figures from year 2014-2015 and visits on-site, an excel-based calculation template was accomplished. During the on-site studies, several visits to the low-level nuclear waste management facilities at Oskarshamn power plant were made, in order to get an overview of how the handling process works. By following the staff around, it was possible to estimate some of the time durations for the different parts in the handling process for compactible lowlevel nuclear waste, that were used in the calculations. The price for compactible low-level nuclear waste was calculated to 6,72 - 6,97 kr/kg, depending on the activity level. The non-compactible low-level nuclear waste price was found to vary between 4 – 48 kr/kg. The large fluctuations are due to different activity levels and associated additional costs in handling, measuring, final deposition etc. For both compactible and non-compactible nuclear waste, the storage cost is a factor that dominates the total cost and that could be minimized. Based on the analysis presented in this work, the cost can be decreased by reducing the storage time and/or store the nuclear waste in a more space efficient way. The cost estimate for free released material is low (5,94 – 8,74 kr/kg), which concludes that Oskarshamn power plant may profit from free releasing as much material as possible, due to the fact that it is highly profitable to recycle metals.

At the Stockholm School of Economics a research programme devoted to the economics of energy and natural resources has been pursued since 1973. The main emphasis has been on the construction and application of quantitative models for studies of energy policy and energy markets. In the programme, models of both energy producing sectors and energy using sectors, as well as applied general equilibrium models of the whole economy, have been constructed. This dissertation is a product of this research programme. The author proposes and applies a specific approach to model integration, i.e. the merger of two or several independently developed models. The approach is intended for integrations of activity analysis sector models and applied general equilibrium models. Model integration makes it possible to extend the range of applicability of applied general equilibrium models by exploiting the information contained in sector models. It also makes it possible to evaluate the validity of the partial equilibrium analyses in which sector models often are employed. The proposed approach is used to integrate a sector model of electricity and heat production with a general equilibrium model of the Swedish economy. Both models have been constructed within the research programme. The author uses the integrated model to look at two issues concerning the role of nuclear power on the Swedish electricity market: What are the likely consequences of a nuclear power discontinuation and how does the nuclear power investment programme of the 1970s and the early 1980s compare with a socially efficient one? / Diss. Stockholm : Handelshögsk.

The fuel cladding is an essential component in the defence-in-depth strategy for nuclear safety. Its integrity and durability are therefore critical for maintaining acceptable safety conditions. However, the integrity of the cladding can be compromised during normal operation due to corrosion and hydriding. To ensure a sufficient level of safety, design and safety criteria have been established to limit oxidation and hydriding. EDF has various multiphysics software tools at its disposal to ensure that these criteria are met. One such tool, CYRANO3, uses oxide thickness measurements from the beginning of the French nuclear industry to model corrosion and hydriding. This study aims to improve CYRANO3 by expanding its validation database and improving its models. The first part of the study focuses on improving the CYRANO3 database by providing a more comprehensive understanding of normal corrosion in a pressurized water reactor, allowing the models to be recalibrated to better represent actual corrosion behaviour.  In the second part, a deeper analysis is conducted to improve the models and increase knowledge of the parameters that influence corrosion. This analysis highlights the significance of temperature and power as input parameters, which will affect the accuracy of CYRANO3 results. Additionally, this study has identified areas for further improvement, including modifications to the implemented corrosion models and a better understanding of the assumptions made about input data. / Brunnkapslingen utgör den första barriären i principen för försvarsdjup. Därför är dess integritet och hållbarhet en prioritet för att upprätthålla acceptabla säkerhetsförhållanden. Integriteten hos brunnskapslingen kan hotas under normal drift genom korrosion och hydridisering. Därför har design- och säkerhetskriterier fastställts för att säkerställa en tillfredsställande säkerhetsnivå genom att begränsa oxidation och hydridisering. EDF har flera multiphysics-program tillgängliga för att säkerställa att dessa kriterier uppfylls. CYRANO3, det program som används i denna studie, baserar sina korrosion- och hydridiseringmodeller på mätningar av oxidthickness som har registrerats sedan starten av den franska kärnkraftsindustrin. Kvaliteten och sanningshalten hos dessa modeller måste testas och uppdateras med den nya erfarenheten av den franska flottan. Denna studie handlar om att förbättra CYRANO3 genom att utöka dess valideringsdatabas och förbättra dess modeller. I den första delen förbättrar förbättringen av CYRANO3-databasen en mer fullständig bild av normal korrosion i en tryckvattenreaktor. Denna utökning gör att modellerna kan recalibreras för att mer exakt återspegla den faktiska korrosionsbeteendet. I den andra delen görs en djupare analys för att förbättra modellerna och öka kunskapen om de parametrar som påverkar korrosionen. Denna analys visar på vikten av temperaturen och kraften som indataparametrar, vilka kommer att definiera kvaliteten på CYRANO3:s resultat. Dessutom har denna studie öppnat upp för nya områden för förbättring, bland annat genom korrigeringar av de implementerade korrosionsmodellerna och en bättre kunskap om antagandena om indatadatan.