Read Books Online and Download eBooks, EPub, PDF, Mobi, Kindle, Text Full Free.
Reactor Spectra Effects On Fission Fragment Cross Sections
Download Reactor Spectra Effects On Fission Fragment Cross Sections full books in PDF, epub, and Kindle. Read online Reactor Spectra Effects On Fission Fragment Cross Sections ebook anywhere anytime directly on your device. Fast Download speed and no annoying ads. We cannot guarantee that every ebooks is available!
Book Synopsis Reactor Spectra Effects on Fission Fragment Cross Sections by : Charles Richard Greenhow
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:
Book Synopsis Nuclear Fission and Neutron-Induced Fission Cross-Sections by : G. D. James
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.
Book Synopsis Neutron Cross Sections and Technology by : David T. Goldman
Download or read book Neutron Cross Sections and Technology written by David T. Goldman and published by . This book was released on 1968 with total page 680 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Studies of the Capture Cross Section of 237Np and 241Am in Different Reactor Spectra by : E. Hellstrand
Download or read book Studies of the Capture Cross Section of 237Np and 241Am in Different Reactor Spectra written by E. Hellstrand and published by . This book was released on 1970 with total page 24 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Fast Reactor Cross Sections by : Shimon Yiftah
Download or read book Fast Reactor Cross Sections written by Shimon Yiftah and published by . This book was released on 1960 with total page 144 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis The Correction of Pebble Bed Reactor Nodal Cross Sections for the Effects of Leakage and Depletion History by : Nathanael Harrison Hudson
Download or read book The Correction of Pebble Bed Reactor Nodal Cross Sections for the Effects of Leakage and Depletion History written by Nathanael Harrison Hudson and published by . This book was released on 2006 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: An accurate and computationally fast method to generate nodal cross sections for the Pebble Bed Reactor (PBR) was presented. In this method, named Spectral History Correction (SHC), a set of fine group microscopic cross section libraries, pre-computed at specified depletion and moderation states, was coupled with the nodal nuclide densities and group bucklings to compute the new fine group spectrum for each node. The relevant fine group cross-section library was then recollapsed to the local broad group cross-section structure with this new fine group spectrum. This library set was tracked in terms of fuel isotopic densities. Fine group modulation factors (to correct the homogeneous flux for heterogeneous effects) and fission spectra were also stored with the cross section library. As the PBR simulation converges to a steady state fuel cycle, the initial nodal cross section library becomes inaccurate due to the burnup of the fuel and the neutron leakage into and out of the node. Because of the recirculation of discharged fuel pebbles with fresh fuel pebbles, a node can consist of a collection of pebbles at various burnup stages. To account for the nodal burnup, the microscopic cross sections were combined with nodal averaged atom densities to approximate the fine group macroscopic cross-sections for that node. These constructed, homogeneous macroscopic cross sections within the node were used to calculate a numerical solution for the fine group spectrum with B1 theory. This new fine spectrum was used to collapse the pre-computed microscopic cross section library to the broad group structure employed by the fuel cycle code. This SHC technique was developed and practically implemented as a subroutine within the PBR fuel cycle code PEBBED. The SHC subroutine was called to recalculate the broad group cross sections during the code convergence. The result was a fast method that compared favorably to the benchmark scheme of cross section calculation with the lattice cross-section generator for two PBR reactor designs.
Book Synopsis Effects of Space-dependent Cross Sections on Core Physics Parameters for Compact Fast Spectrum Space Power Reactors by :
Download or read book Effects of Space-dependent Cross Sections on Core Physics Parameters for Compact Fast Spectrum Space Power Reactors written by and published by . This book was released on 1987 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Effects of multigroup neutron cross section generation procedures on core physics parameters for compact fast spectrum reactors have been examined. Homogeneous and space-dependent multigroup cross section sets were generated in 11 and 27 groups for a representative fast reactor core. These cross sections were used to compute various reactor physics parameters for the reference core. Coarse group structure and neglect of space-dependence in the generation procedure resulted in inaccurate computations of reactor flux and power distributions and in significant errors regarding estimates of core reactivity and control system worth. Delayed neutron fraction was insensitive to cross section treatment, and computed reactivity coefficients were only slightly sensitive. However, neutron lifetime was found to be very sensitive to cross section treatment. Deficiencies in multigroup cross sections are reflected in core nuclear design and, consequently, in system mechanical design.
Book Synopsis Cross Sections for Reactor Analysis by :
Download or read book Cross Sections for Reactor Analysis written by and published by . This book was released on 1964 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: A listing of the data on the revised tape is presented. The nuclear data are a reproduction of the computer printout. Other nuclear data (spectra, energy, absorption cross section of some poisons and absorption and fission cross sections of selected fuel materials) were transcribed from the tape listing to provide a more compact format or to allow easier comparison of absorbers and fuels. (auth).
Book Synopsis Reactor Physics Constants by : Reactor Physics Constants Center (U.S.)
Download or read book Reactor Physics Constants written by Reactor Physics Constants Center (U.S.) and published by . This book was released on 1963 with total page 880 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book NBS Special Publication written by and published by . This book was released on 1968 with total page 682 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Comprehensive Nuclear Materials by : Todd R Allen
Download or read book Comprehensive Nuclear Materials written by Todd R Allen and published by Elsevier. This book was released on 2011-05-12 with total page 3552 pages. Available in PDF, EPUB and Kindle. Book excerpt: Comprehensive Nuclear Materials, Five Volume Set discusses the major classes of materials suitable for usage in nuclear fission, fusion reactors and high power accelerators, and for diverse functions in fuels, cladding, moderator and control materials, structural, functional, and waste materials. The work addresses the full panorama of contemporary international research in nuclear materials, from Actinides to Zirconium alloys, from the worlds' leading scientists and engineers. Critically reviews the major classes and functions of materials, supporting the selection, assessment, validation and engineering of materials in extreme nuclear environment Fully integrated with F-elements.net, a proprietary database containing useful cross-referenced property data on the lanthanides and actinides Details contemporary developments in numerical simulation, modelling, experimentation, and computational analysis, for effective implementation in labs and plants
Book Synopsis Nuclear Data for Science and Technology by : Syed M. Qaim
Download or read book Nuclear Data for Science and Technology written by Syed M. Qaim and published by Springer Science & Business Media. This book was released on 2012-12-06 with total page 1041 pages. Available in PDF, EPUB and Kindle. Book excerpt: This book describes the Proceedings of the International Conference on Nuclear Data for Science and Technology held at Jillich in May 1991. The conference was in a series of application oriented nuclear data conferences organized in the past under the auspices of the Nuclear Energy Agency-Nuclear Data Committee (NEANDC) and with the support of the Nuclear Energy Agency-Committee on Reactor Physics (NEACRP). It was the fIrst international conference on nuclear data held in Germany, with the scientific responsibility entrusted to the Institute of Nuclear Chemistry of the Research Centre Jillich. The scientific programme was established by the International Programme Committee in consultation with the International Advisers, and the NEA and IAEA cooperated in the organization. A total of 328 persons from 37 countries and fIve international organizations participated. The scope of these Proceedings extends to a wide range of interdisciplinary topics dealing with measu rement, calculation, evaluation and application of nuclear data, with a major emphasis on numerical data. Both energy and non-energy related applications are considered and due attention is given to some fundamental aspects relevant to the understanding of nuclear data.
Book Synopsis Neutron Resonance Theory by : Richard N. Hwang
Download or read book Neutron Resonance Theory written by Richard N. Hwang and published by . This book was released on 2020-08-17 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1975 with total page 744 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Time-dependent Fission-product Thermal and Resonance Absorption Cross Sections by : T. R. England
Download or read book Time-dependent Fission-product Thermal and Resonance Absorption Cross Sections written by T. R. England and published by . This book was released on 1962 with total page 72 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Nuclear Cross Sections and Technology by : Roald A. Schrack
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 Nuclear Science Abstracts written by and published by . This book was released on 1974-03 with total page 1100 pages. Available in PDF, EPUB and Kindle. Book excerpt: