![]() Then, it illustrates the typical composition of nuclear spent fuel, the time evolution of its radioactivity, and the safe methods for its final disposal. It first gives the classification of nuclear wastes according to their radioactive content and half-life, making comparisons with other hazardous waste and waste from other sources of electricity generation. This chapter focuses on nuclear waste generation, handling, storage and disposal. Various types of radioactive waste exist and proper disposal depends on the properties of the waste. Therefore, radioactive wastes must be handled in a safe way to protect people and the environment. However, it generates radioactive wastes in solid, liquid, and gaseous forms that can contaminate the environment and create a hazard for people’s health if not properly controlled and managed. View projectĮlectricity production from nuclear power does not emit greenhouse gases like carbon dioxide into the air. #FISSION ENERGY FULL#This should reduce both the computational demands and the time needed to the full R&D process, due to (at least partial) use of computational methodologies that are optimized for the different physical processes involved and to the removal of the need for a validation phase, which has been carried on along decades for each of the codes.Īs a parallel task we will realize – in a well delimited context, superconducting magnets quench studies – a specific and directly multiscale/multiphysics simulation tool.Ĭrosscheck among these two cases will give useful information about respective qualities and lacks: performances will be directly comparable, at each stage, because both will be developed on the same platform. #FISSION ENERGY SOFTWARE#We propose to develop and optimize an "intermediate" approach: parallelization and (partial) integration of existing and reliable computational/simulation codes, by using the newest hardware and software technologies. Our goal is the study and the development of parallel computing technologies useful to the description of multiscale/multiphysics phenomena in the broad field of energy production and distribution: complex systems modelization usually is grounded on a variety of physical models, because of the wide differences in the scales at which different physical phenomena occur. It should be noted that nuclear power is not directly emitting greenhouse gas emissions, but rather that lifecycle emissions occur through plant construction, operation, uranium mining and milling, and plant decommissioning. The article then explains some of the factors responsible for the disparity in lifecycle estimates, in particular identifying errors in both the lowest estimates (not comprehensive) and the highest estimates (failure to consider co-products). It calculates that while the range of emissions for nuclear energy over the lifetime of a plant, reported from qualified studies examined, is from 1.4 g of carbon dioxide equivalent per kWh (g CO2e/kWh) to 288 g CO2e/kWh, the mean value is 66 g CO2e/kWh. It begins by briefly detailing the separate components of the nuclear fuel cycle before explaining the methodology of the survey and exploring the variance of lifecycle estimates. This article screens 103 lifecycle studies of greenhouse gas-equivalent emissions for nuclear power plants to identify a subset of the most current, original, and transparent studies. The potential advantage of the Thorium cycle is discussed as well as different scenarios that could be used to implement it. Finally, the last chapter deals with the examination of proposed and possible waste transmutation policies and the role which could be played by ADSR in this context. The book also evaluates a number of practical designs that have been proposed. The conditions for having a constant reactivity over sufficiently long lapse of time are also discussed. The discussion of the fuel evolution follows with its relevance to safety and to the waste production and incineration. The possibility to optimize the source importance is examined in detail. A thorough discussion is given on the size of hybrid reactors, which follows very different constraints from that of critical reactors. It examines the specifics of ADSR, starting from the neutron spallation source to safety features. ![]() The book then presents computational methods, with special emphasis on Monte Carlo methods. It proceeds by developing the elementary physics of neutron reactors, including the basic nuclear physics involved. ![]() Since hybrid reactors may contribute to future nuclear energy production, the book begins with a discussion of the general energy problem. This book describes the basic knowledge in nuclear, neutron, and reactor physics necessary for understanding the principle and implementation of accelerator driven subcritical nuclear reactors (ADSRs), also known as hybrid reactors. ![]()
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