Thermal Hydraulics Of Accident Tolerant Fuel Concepts And A Preliminary Demonstration Of Casls Coupled Tools For Bwrs
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| Total Pages | : |
| Release | : 2015 |
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Iron-chromium-aluminum (FeCrAl) alloys are being considered for fuel concepts with enhanced accident tolerance. FeCrAl alloys have very slow oxidation kinetics and good strength at high temperatures. FeCrAl could be used for fuel cladding in light water reactors and/or as channel box material in boiling water reactors (BWRs). To estimate the potential safety gains afforded by the FeCrAl concept, the MELCOR code was used to analyze a range of postulated station blackout severe accident scenarios in a BWR/4 reactor employing FeCrAl. The simulations utilize the most recently known thermophysical properties and oxidation kinetics for FeCrAl. Overall, when compared to the traditional Zircaloy-based cladding and channel box, the FeCrAl concept provides a few extra hours of time for operators to take mitigating actions and/or for evacuations to take place. A coolable core geometry is retained longer, enhancing the ability to stabilize an accident. Finally, due to the slower oxidation kinetics, substantially less hydrogen is generated, and the generation is delayed in time. This decreases the amount of non-condensable gases in containment and the potential for deflagrations to inhibit the accident response.
| Author | : Joaquín Rubén Basualdo Perelló |
| Publisher | : |
| Total Pages | : |
| Release | : 2020* |
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| ISBN | : |
| Author | : International Atomic Energy Agency |
| Publisher | : |
| Total Pages | : 218 |
| Release | : 2020-07-30 |
| Genre | : |
| ISBN | : 9789201080202 |
This publication is the result of an IAEA technical meeting and reports on Member States' capabilities in modelling, predicting and improving their understanding of the behaviour of nuclear fuel under accident conditions. The main results and outcomes of a coordinated research project (CRP) on this topic are also presented.
| Author | : OECD Nuclear Energy Agency |
| Publisher | : OECD Publishing |
| Total Pages | : 74 |
| Release | : 2001 |
| Genre | : Technology & Engineering |
| ISBN | : |
Presents brief descriptions of 20 fuel-related safety criteria along with both the rationale for having such criteria and possible new design and operational issues which could have an effect on them.
| Author | : International Atomic Energy Agency |
| Publisher | : IAEA |
| Total Pages | : 656 |
| Release | : 2005 |
| Genre | : Business & Economics |
| ISBN | : |
Describes the state of knowledge of natural circulation in water cooled nuclear power plants and passive system reliability. The publication presents information on phenomena, models, predictive tools and experiments that currently support design and analysis of natural circulation systems, and highlights areas where additional research is needed.
| Author | : Robert Martin |
| Publisher | : World Scientific |
| Total Pages | : 717 |
| Release | : 2019-02-13 |
| Genre | : Technology & Engineering |
| ISBN | : 9813275677 |
This book captures the principles of safety evaluation as practiced in the regulated light-water reactor nuclear industry, as established and stabilized over the last 30 years. It is expected to serve both the current industry and those planning for the future. The work's coverage of the subject matter is the broadest to date, including not only the common topics of modeling and simulation, but also methods supporting the basis for the underlying assumptions, the extension to radiological safety, what to expect in a licensing review, historical perspectives and the implication for new designs.This text is an essential resource for practitioners and students, on the current best-practices in nuclear power plant safety and their basis. Contributors of this work are subject matter experts in their specialties, much of which was nurtured and inspired by Prof. Larry Hochreiter, a prominent nuclear safety pioneer.Related Link(s)
| Author | : Ottmar Edenhofer |
| Publisher | : Cambridge University Press |
| Total Pages | : 1088 |
| Release | : 2011-11-21 |
| Genre | : Science |
| ISBN | : 9781107607101 |
This Intergovernmental Panel on Climate Change Special Report (IPCC-SRREN) assesses the potential role of renewable energy in the mitigation of climate change. It covers the six most important renewable energy sources - bioenergy, solar, geothermal, hydropower, ocean and wind energy - as well as their integration into present and future energy systems. It considers the environmental and social consequences associated with the deployment of these technologies, and presents strategies to overcome technical as well as non-technical obstacles to their application and diffusion. SRREN brings a broad spectrum of technology-specific experts together with scientists studying energy systems as a whole. Prepared following strict IPCC procedures, it presents an impartial assessment of the current state of knowledge: it is policy relevant but not policy prescriptive. SRREN is an invaluable assessment of the potential role of renewable energy for the mitigation of climate change for policymakers, the private sector, and academic researchers.
| Author | : Lino Guzzella |
| Publisher | : Springer Science & Business Media |
| Total Pages | : 345 |
| Release | : 2007-09-21 |
| Genre | : Technology & Engineering |
| ISBN | : 3540746927 |
The authors of this text have written a comprehensive introduction to the modeling and optimization problems encountered when designing new propulsion systems for passenger cars. It is intended for persons interested in the analysis and optimization of vehicle propulsion systems. Its focus is on the control-oriented mathematical description of the physical processes and on the model-based optimization of the system structure and of the supervisory control algorithms.
| Author | : Willem Frederik Geert van Rooijen |
| Publisher | : IOS Press |
| Total Pages | : 160 |
| Release | : 2006 |
| Genre | : Technology & Engineering |
| ISBN | : 9781586036966 |
The Generation IV Forum is an international nuclear energy research initiative aimed at developing the fourth generation of nuclear reactors, envisaged to enter service halfway the 21st century. One of the Generation IV reactor systems is the Gas Cooled Fast Reactor (GCFR), the subject of study in this thesis. The Generation IV reactor concepts should improve all aspects of nuclear power generation. Within Generation IV, the GCFR concept specifically targets sustainability of nuclear power generation. The Gas Cooled Fast Reactor core power density is high in comparison to other gas cooled reactor concepts. Like all nuclear reactors, the GCFR produces decay heat after shut down, which has to be transported out of the reactor under all circumstances. The layout of the primary system therefore focuses on using natural convection Decay Heat Removal (DHR) where possible, with a large coolant fraction in the core to reduce friction losses.
| Author | : International Atomic Energy Agency |
| Publisher | : |
| Total Pages | : 0 |
| Release | : 2009 |
| Genre | : Nuclear reactors |
| ISBN | : 9781523129898 |
For more than 50 years research reactors have played an important role in the development of nuclear science and technology. They have made significant contributions to a large number of disciplines, as well as to the educational and research programmes of about 70 countries worldwide. There are substantial utilization issues being faced by the research reactor community, including the selection, design and operation of various types of devices in research reactors. This publication has been prepared by the IAEA to facilitate the exchange of ideas, concepts and experience. It presents descriptions of design and utilization features of facilities and associated devices that are implemented in different research reactors worldwide, covering selected fields of application.
