Download or read book Temperature Effects Upon Nuclear Cross Sections written by Edward Harris Klevans and published by . This book was released on 1958 with total page 160 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Temperature Dependent Scattering Cross Section Effects on Nuclear Reactor Control written by Charles Leon Biggs and published by . This book was released on 1968 with total page 102 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Nuclear Cross Sections for Technology written by Joseph L. Fowler and published by . This book was released on 1980 with total page 1056 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Temperature dependent and Multi level Effects on Neutron Resonance Cross Sections written by Thomas E. Shea and published by . This book was released on 1974 with total page 242 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Nuclear Fission and Neutron Induced Fission Cross Sections written by G. D. James and published by Elsevier. This book was released on 2013-10-22 with total page 294 pages. Available in PDF, EPUB and Kindle. Book excerpt: Nuclear Fission and Neutron-Induced Fission Cross-Sections is the first volume in a series on Neutron Physics and Nuclear Data in Science and Technology. This volume serves the purpose of providing a thorough description of the many facets of neutron physics in different fields of nuclear applications. This book also attempts to bridge the communication gap between experts involved in the experimental and theoretical studies of nuclear properties and those involved in the technological applications of nuclear data. This publication will be invaluable to those interested in studying nuclear fission and neutron-induced fission cross-sections, as well as other relevant concepts.
Download or read book Nuclear Cross Sections and Technology written by Roald A. Schrack and published by . This book was released on 1975 with total page 564 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Measured Dependence of Some Effective Cross Sections on Thermal Neutron Temperatures in the Range 195 C to 20 C written by Atomic Energy of Canada Limited and published by Chalk River, Ont. : Chalk River Nuclear Laboratories. This book was released on 1985 with total page 50 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Reports to the AEC Nuclear Cross Sections Advisory Group written by and published by . This book was released on 1960-09 with total page 92 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Dependence of Effective Cross Sections on Thermal Neutron Temperatures written by Jones, R. T and published by Chalk River, Ont. : Reactor Physics Branch, Chalk River Nuclear Laboratories. This book was released on 1979 with total page 45 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Treatment of Nuclear Data for Transport Problems Containing Detailed Temperature Distributions written by and published by . This book was released on 2006 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: This work considers the problem of accurately representing the temperature dependence of neutron cross-section data in neutron transport problems when there are many nuclides and when the temperature distributions vary significantly with both space and time. An approach involving interpolation between nuclear data libraries at various reference temperatures is investigated. Reference nuclear data libraries are obtained by Doppler broadening cross sections to the desired temperatures using the NJOY code system. Several interpolation schemes over various temperature intervals are studied. Interpolated values at intermediate temperatures are compared to NJOY Doppler broadened results for the same temperature. Differences relative to the Doppler broadened results are calculated in order to judge the suitability of the interpolation scheme and temperature interval. The total, elastic scattering, capture, and fission (if applicable) reactions for 238U, 235U, natural Zr, 16O, 1°B and 1H are considered in this study, over a temperature range of 294 K to 811 K ((almost equal to)70 F to (almost equal to)1000 F). The nuclides and temperature range are selected to best represent typical light water reactor calculations. This work covers only the free-atom cross section and does not explore the many nuances of temperature treatment of nuclear data in the thermal energy range for nuclides where molecular binding effects are significant, e.g., water, beryllium, graphite. Additionally, dilute-average cross sections are used in the unresolved resonance range (URR) for this study. Temperature treatment of probabilistic methods used to construct cross sections in the URR are not considered for this work. The study shows that cross sections can be interpolated within an accuracy of 0.1% over a temperature interval of 111 K (200 F) for 1H, 1°B, and 16O. Smaller intervals are required for nuclides with more complex resonance behavior. Some values of the interpolated cross sections for natural Zr, 238U and 235U, remain greater than the target 0.1% relative difference even with a 28 K (50 F) interval, suggesting a smaller interval is necessary for these nuclides.
Download or read book Thermal Neutron Scattering written by Peter A. Egelstaff and published by . This book was released on 1965 with total page 548 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Reactor Spectra Effects on Fission Fragment Cross Sections written by Charles Richard Greenhow and published by . This book was released on 1959 with total page 36 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Physics of High Temperature Reactors written by Luigi Massimo and published by Elsevier. This book was released on 2013-10-22 with total page 249 pages. Available in PDF, EPUB and Kindle. Book excerpt: Physics of High-Temperature Reactors focuses on the physics of high-temperature reactors (HTRs) and covers topics ranging from fuel cycles and refueling strategies to neutron cross-sections, transport and diffusion theory, and resonance absorption. Spectrum calculations and cross-section averaging are also discussed, along with the temperature coefficient and reactor control. Comprised of 16 chapters, this book begins with a general description of the HTR core as well as its performance limitations. The next chapter deals with general considerations about HTR physics, including quantities to be determined and optimized in the design of nuclear reactors. Potential scattering and resonance reactions between neutrons and atomic nuclei are then considered, together with basic aspects of transport and diffusion theory. Subsequent chapters explore methods for solving the diffusion equation; slowing-down and neutron thermalization in graphite; HTR core design, fuel management, and cost calculations; and core dynamics and accident analysis. The final chapter describes the sequence of reactor design calculations. This monograph is written primarily for students of HTR physics who are preparing to enter the field as well as technologists of other disciplines who are working on the system.
Download or read book Modelling of Nuclear Reactor Multi physics written by Christophe Demazière and published by Academic Press. This book was released on 2019-11-19 with total page 370 pages. Available in PDF, EPUB and Kindle. Book excerpt: Modelling of Nuclear Reactor Multiphysics: From Local Balance Equations to Macroscopic Models in Neutronics and Thermal-Hydraulics is an accessible guide to the advanced methods used to model nuclear reactor systems. The book addresses the frontier discipline of neutronic/thermal-hydraulic modelling of nuclear reactor cores, presenting the main techniques in a generic manner and for practical reactor calculations.The modelling of nuclear reactor systems is one of the most challenging tasks in complex system modelling, due to the many different scales and intertwined physical phenomena involved. The nuclear industry as well as the research institutes and universities heavily rely on the use of complex numerical codes. All the commercial codes are based on using different numerical tools for resolving the various physical fields, and to some extent the different scales, whereas the latest research platforms attempt to adopt a more integrated approach in resolving multiple scales and fields of physics. The book presents the main algorithms used in such codes for neutronic and thermal-hydraulic modelling, providing the details of the underlying methods, together with their assumptions and limitations. Because of the rapidly expanding use of coupled calculations for performing safety analyses, the analysists should be equally knowledgeable in all fields (i.e. neutron transport, fluid dynamics, heat transfer).The first chapter introduces the book's subject matter and explains how to use its digital resources and interactive features. The following chapter derives the governing equations for neutron transport, fluid transport, and heat transfer, so that readers not familiar with any of these fields can comprehend the book without difficulty. The book thereafter examines the peculiarities of nuclear reactor systems and provides an overview of the relevant modelling strategies. Computational methods for neutron transport, first at the cell and assembly levels, then at the core level, and for one-/two-phase flow transport and heat transfer are treated in depth in respective chapters. The coupling between neutron transport solvers and thermal-hydraulic solvers for coarse mesh macroscopic models is given particular attention in a dedicated chapter. The final chapter summarizes the main techniques presented in the book and their interrelation, then explores beyond state-of-the-art modelling techniques relying on more integrated approaches. - Covers neutron transport, fluid dynamics, and heat transfer, and their interdependence, in one reference - Analyses the emerging area of multi-physics and multi-scale reactor modelling - Contains 71 short videos explaining the key concepts and 77 interactive quizzes allowing the readers to test their understanding
Download or read book Neutron Cross Sections written by Victoria McLane and published by Elsevier. This book was released on 2012-12-02 with total page 850 pages. Available in PDF, EPUB and Kindle. Book excerpt: Neutron Cross Sections, Volume 2: Neutron Cross Section Curves presents data for total reaction cross sections and related fission parameters as a function of incident-neutron energy. This book covers energy range from 0.01 eV to 200 MeV to exclude crystalline and magnetic effects for slow neutrons and relativistic effects for high energy neutrons. The data in this volume are grouped into sections corresponding to the element of the target nucleus in the neutron-induced reaction. These sections are ordered in increasing atomic number. Within a section, graphical data are presented for the natural element followed by the isotopes of that element in order of increasing atomic mass. A list of the reaction types is provided at the end of each section. This book also provides graphical section, wherein each graphical page is annotated on the outer edge with a symbol for an element or isotope followed by the list of the cross section data for that element or isotope. The data plotted in the graphical section are tagged by a mnemonic consisting of year, laboratory, and author's last name. This tag can be used to find the corresponding reference on the bibliographic pages.
Download or read book POINT 2007 written by and published by . This book was released on 2007 with total page 27 pages. Available in PDF, EPUB and Kindle. Book excerpt: This report is one in the series of ''POINT'' reports that over the years have presented temperature dependent cross sections for the then current version of ENDF/B. In each case I have used publicly available nuclear data (the current ENDF/B data, available online at the National Nuclear Data Center, Brookhaven National Laboratory http://www.nndc.bnl.gov/) and publicly available computer codes (the current PREPRO codes, available on-line at the Nuclear Data Section, IAEA, Vienna, Austria http://wwwnds. iaea.or.at/ndspub/endf/prepro/). I have used these in combination to produce the temperature dependent cross sections used in applications and presented in this report. The preceding POINT 2004 report [R1] presented results for the now frozen last version of ENDF/B-VI, Release 8. The current POINT 2007 report is based on data from recently released ENDF/B-VII.0, which is the first release of ENDF/B-VII.
Download or read book Proceedings written by Conference on Neutron Cross Section Technology and published by . This book was released on 1966 with total page 576 pages. Available in PDF, EPUB and Kindle. Book excerpt:
