Demonstration Of A Full Core Reactivity Equivalence For Fecral Enhanced Accident Tolerant Fuel In Bwrs
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Author | : James J. Duderstadt |
Publisher | : Wiley |
Total Pages | : 0 |
Release | : 1991-01-16 |
Genre | : Technology & Engineering |
ISBN | : 9780471223634 |
Classic textbook for an introductory course in nuclear reactor analysis that introduces the nuclear engineering student to the basic scientific principles of nuclear fission chain reactions and lays a foundation for the subsequent application of these principles to the nuclear design and analysis of reactor cores. This text introduces the student to the fundamental principles governing nuclear fission chain reactions in a manner that renders the transition to practical nuclear reactor design methods most natural. The authors stress throughout the very close interplay between the nuclear analysis of a reactor core and those nonnuclear aspects of core analysis, such as thermal-hydraulics or materials studies, which play a major role in determining a reactor design.
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 | : Ian Crossland |
Publisher | : Elsevier |
Total Pages | : 649 |
Release | : 2012-09-21 |
Genre | : Business & Economics |
ISBN | : 0857096389 |
The nuclear fuel cycle is characterised by the wide range of scientific disciplines and technologies it employs. The development of ever more integrated processes across the many stages of the nuclear fuel cycle therefore confronts plant manufacturers and operators with formidable challenges. Nuclear fuel cycle science and engineering describes both the key features of the complete nuclear fuel cycle and the wealth of recent research in this important field.Part one provides an introduction to the nuclear fuel cycle. Radiological protection, security and public acceptance of nuclear technology are considered, along with the economics of nuclear power. Part two goes on to explore materials mining, enrichment, fuel element design and fabrication for the uranium and thorium nuclear fuel cycle. The impact of nuclear reactor design and operation on fuel element irradiation is the focus of part three, including water and gas-cooled reactors, along with CANDU and Generation IV designs. Finally, part four reviews spent nuclear fuel and radioactive waste management.With its distinguished editor and international team of expert contributors, Nuclear fuel cycle science and engineering provides an important review for all those involved in the design, fabrication, use and disposal of nuclear fuels as well as regulatory bodies and researchers in this field. - Provides a comprehensive and holistic review of the complete nuclear fuel cycle - Reviews the issues presented by the nuclear fuel cycle, including radiological protection and security, public acceptance and economic analysis - Discusses issues at the front-end of the fuel cycle, including uranium and thorium mining, enrichment and fuel design and fabrication
Author | : Rocco F. Iuorno |
Publisher | : |
Total Pages | : 72 |
Release | : 1969 |
Genre | : Monte Carlo method |
ISBN | : |
Author | : |
Publisher | : |
Total Pages | : 244 |
Release | : 1959 |
Genre | : Nuclear fuels |
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 | : Xingbo Liu |
Publisher | : Springer |
Total Pages | : 440 |
Release | : 2017-03-06 |
Genre | : Technology & Engineering |
ISBN | : 3319523333 |
This collection highlights materials research and innovations for a wide breadth of energy systems and technologies. The volume includes papers organized into the following sections:Energy and Environmental Issues in Materials Manufacturing and ProcessingMaterials in Clean PowerMaterials for Coal-Based PowerMaterials for Energy Conversion with Emphasis on SOFCMaterials for Gas TurbinesMaterials for Nuclear EnergyMaterials for Oil and Gas
Author | : M. J. Driscoll |
Publisher | : |
Total Pages | : 270 |
Release | : 1990 |
Genre | : Technology & Engineering |
ISBN | : |
The Linear Reactivity Model (LRM) is a simple nuclear fuel management model that comes with a diskette containing three programs. Consisting of a collection of algorithms and methods, the LRM describes complex core behavior, but it is simpler than the complex programs developed for design calculations. This makes the LRM particularly useful as a teaching tool to explain the basic principles of nuclear fuel management. The LRM mainly focuses on the pressurized water reactor, but it is also directly applicable to the boiling water reactor. Application of the LRM to the CANDU reactor is also covered.
Author | : |
Publisher | : OECD Publishing |
Total Pages | : 562 |
Release | : 2005 |
Genre | : Business & Economics |
ISBN | : |
This publication sets out the findings of an international seminar, held in Aix-en-Provence, France in March 2004, which considered recent progress in the field of pellet-clad interaction in light water reactor fuels. It also reviews current understanding of relevant phenomena and their impact on the nuclear fuel rod under the widest possible conditions, and about both uranium-oxide and mixed-oxide fuels.
Author | : David John Young |
Publisher | : Elsevier |
Total Pages | : 593 |
Release | : 2008-10-03 |
Genre | : Business & Economics |
ISBN | : 008044587X |
The book is concerned with understanding the fundamental mechanisms of high temperature alloy oxidation. It uses this understanding to develop methods of predicting oxidation rates and the way they change with temperature, gas chemistry and alloy composition. The focus is on designing (or selecting) alloy compositions which provide optimal resistance to attack by corrosive gases. . Emphasises quantitative calculations for predicting reaction rates and the effects of temperature, oxidant activities and alloy compositions. . Uses phase diagrams and diffusion paths to analyse and interpret scale structures and internal precipitation distributions . Provides a detailed examination of corrosion in industrial gases (water vapour effects, carburisation and metal dusting, sulphidation) . Text is well supported by numerous micrographs, phase diagrams and tabulations of relevant thermodynamic and kinetic data . Combines physical chemistry and materials science methodologies.