The bachelor's thesis is the culmination of the program. The students develop, enhance, and demonstrate their methodological abilities to independently tackle and solve a given research problem. The thesis furnishes the students with their first major research experience, and is a further development of the work done in the basis courses, and usually, the focused study.

Comprehensive knowledge is provided on the phenomena during a Beyond Design Bases Accident (BDBA) in a Nuclear Power Plants (NPP), on their modeling as well as on countermeasures taken against radioactive releases into the environment, both by Severe Accident Management Guidelines (SAMG), together with technical backfitting measures in existing plants and an extended design of new NPP.

The course deals with fundamentals of the application of Computational Fluid Dynamics to gas-liquid flows as well as particle laden gas flows including aerosols. The course will present the current state of art in the field. Challenging examples, mainly from the fluid-machinery and plant, are discussed in detail.

The course is held at PSI in the form of a block intensive course (full day lectures).Introduction to aspects of Nuclear Power Plant decommissioning including project planning and management, costs and financing, radiological characterization, dismantling/decontamination technologies, safety aspects and radioactive waste management considerations.

Fundamentals of thermal sciences, linked to energy conversion

The course presents an overview of measurement tasks in engineering environments. Different concepts for the acquisition and processing of typical measurement quantities are introduced. Following an initial in-class introduction, laboratory exercises from different application areas (especially in thermofluidics, energy, and process engineering) are attended by students in small groups.

Physical and chemical aspects of the synthesis and distribution of uranium, radioactive decay and detection, uranium production, uranium enrichment, nuclear fuel production, reprocessing of spent fuel, nuclear waste disposal and final deep geological repository

Introduction to fluid flows with multiple interacting phases. The emphasis is on regimes where a dispersed phase is carried by a continuous one: e.g., particles, bubbles and droplets suspended in gas or liquid flows, laminar or turbulent. The flow physics is put in the context of natural, biological, and industrial problems.

Phyisical fundamentals of the fission reaction and the sustainable chain reaction, thermal design, construction, function and operation of nuclear reactors and power plants, light water reactors and other reactor types, conversion and breeding, radioactive dose and limits, nuclear waste.

Experiments on a nuclear training reactor and power plant simulators provide detailed knowledge on construction, function and dynamics of nuclear reactors and nuclear power plants during transients and accidents.

No description available.

Basic heat removal phenomena in a reactor core, limits for heat generation and technological consequences arising from fuel, cladding and coolant properties, main principles of reactor thermal design, as well as the general design of the nuclear power plant with its main and auxiliary systems are explained. The system technology of the most important thermal and fast reactor types is introduced.

Knowledge about safety concepts and requirements of nuclear power plants and their implementation in deterministic safety concepts and safety systems. Knowledge about behavior under accident conditions and about the methods of probabilistic risk analysis and how to handle results. Introduction into key elements of the enhanced safety of nuclear systems for the future.

Current advanced research activities in the areas of thermo- and fluid dynamics are presented and discussed, mostly by external speakers.

Introduction to the fundamentals of technical thermodynamics.