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This article is dedicated to the various nuclear reactor systems and to the issues that are currently dominant and will be in the near future. The following are reviewed: the proven systems of the current fleet, dominated by LWRs ; proven but pending systems, including liquid metal cooled FRs ; the MSR ; the SMR way. Regeneration of fissile nuclei is analyzed in terms of core physics (h parameter) and in terms of consequences, boosting the life expectancy of nuclear fission. The economics of nuclear power are then examined, from « historical » nuclear power to the horizon of 2050, with an extension to the evaluation of energy mixes, leading to the consideration of intermittency and its price.
Today's nuclear reactors (boilers and fuel), originated in the effervescence of the 1940s. They improved over successive Generations of nuclear reactor systems. After describing the various architectures, analysis of the main constraints on fission (safety, competitiveness, resources, waste) leads to identify the strong coupling between the reactor and the fuel cycle as essential to the sustainability of fission energy on a human scale, thanks to the regeneration of fissile nuclei. In the very long term, the nuclear energy continuum (fusion, fission, accelerated charged particles) turns out to be renewable.
This article is the first part of a two part review presenting the nuclear data evaluation process. It describes the present state of the theoretical knowledge of the nuclear physics processes involved in reactor physics. During the evaluation process, the theoretical and experimental knowledge is distilled and synthetized into the files used by simulation codes. After an overview of the content of the evaluated files, the different methods used for nuclear data evaluation are described. We will mainly focus on modeling. This review is illustrated by examples chosen from everyday practice of nuclear data evaluation.
Firstly the main French nuclear sites, the facilities located on these sites and the main radionuclides that they are authorized to release in the environment by atmospheric and liquid ways are presented. The relationships between the released activities, the radiological activities measured in the various components of the environment (air, water, soils, foodstuffs, etc.) and the resulting doses which can be received by the surrounding populations are then developed.
This article is the first one in a series of three articles dedicated to radioecology. After an introduction to the field covered by radioecology, it deals with the dispersion of radionuclides in air, their deposition on surfaces, their migration in soils and their dispersion in watercourses. For each mode of transfer, the associated phenomena are firstly presented, followed by the parameters or the models that allow to take them into account. Quantitative illustrations and parameter values showthe intensity of these transfers and to make rough assessments of volumic, surfacic or massic activities in the concerned environmental components.
This article presents the mechanisms of water-induced alteration of silicate glasses with a special focused on those for nuclear waste containment. It details the influence of various key parameters, such as temperature, pH, and changes in the composition of both the glasses and the solution, on these mechanisms, and explains how the competition between different alteration processes leads to kinetics that may vary over several orders of magnitude. The experimental methods that can be used to quantify the alteration kinetics of glasses are also presented.
The stringent demands for safety, reliability, and durability that are intrinsic to the nuclear industry have motivated the choice of specific metallic materials. In this context, the current article details the main metallic materials used in the construction of pressurized water reactors (PWRs), including their development and recent technological advancements. After presenting the general material requirements for nuclear reactor structural materials, the technical solutions developed to meet the specific needs of the PWR fleet, by considering various components of the primary and secondary circuits, are discussed. Emerging manufacturing processes for these components are also addressed.
This article first introduces the reader to the two types of space nuclear propulsion systems currently being developed: thermal and electric, by presenting their principles, the performance gains they offer over current technologies and the space applications/missions for which they may offer decisive advantages. The second part of the article focuses on space nuclear thermal propulsion engines, addressing design, development and qualification options and issues and the associated technological and programmatic challenges.
This article begins by presenting the various types of space mission for which space nuclear fission power systems (SNFPSs) offer proven or potential advantages over alternative technologies. It outlines the space-application-specific requirements that SNFPSs must meet. It reviews the main past and current development programs, describing the main characteristics of the SNFPSs involved, the results obtained, and the lessons that can be learned from them. It then goes on to discuss the merits and limitations of the various possible design and technological options for the main subsystems making up a SNFPS. Safety aspects of these SNFPSs during launch and orbit, space operation and post-operation phases are also covered.
The Cigéo project will be designed to dispose, in an underground facility located in a geological layer, high and long-lived intermediate radioactive waste produced by French facilities since the beginning of nuclear programs until today. The Cigéo disposal will be in operation for around one hundred years. During this period and far beyond it - the safety of the facility will have to be maintained and radioactivity confined to protect human beings and the environment. For over 30 years, Andra has been carrying out research and development work. In the context of the high-level waste cells, R&D work is studying the evolution of the main metallic components of this cell, the liner and the overpack, under the combined effect of corrosion and mechanical processes.
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