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Availability Of Endf B Neutron Cross Section Data
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Book Synopsis AVAILABILITY OF ENDF/B NEUTRON CROSS SECTION DATA. by :
Download or read book AVAILABILITY OF ENDF/B NEUTRON CROSS SECTION DATA. written by and published by . This book was released on 1968 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Availability of ENDF/B Neutron Cross Section Data by :
Download or read book Availability of ENDF/B Neutron Cross Section Data written by and published by . This book was released on 1968 with total page 50 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis ENDF/B Neutron Cross-section Data for Natural Helium (ENDF-125) by : E. M. Pennington
Download or read book ENDF/B Neutron Cross-section Data for Natural Helium (ENDF-125) written by E. M. Pennington and published by . This book was released on 1968 with total page 36 pages. Available in PDF, EPUB and Kindle. Book excerpt:
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 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 736 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Program RECENT (version 79-1) by : Dermott Edward Cullen
Download or read book Program RECENT (version 79-1) written by Dermott Edward Cullen and published by . This book was released on 1979 with total page 44 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Continuous Energy Neutron Cross Section Data Tables Based Upon ENDF/B-VII. 1 by :
Download or read book Continuous Energy Neutron Cross Section Data Tables Based Upon ENDF/B-VII. 1 written by and published by . This book was released on 2013 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Evaluation of 235U Neutron Cross Section and Gamma Ray Production for ENDF/B-V by : M. R. Bhat
Download or read book Evaluation of 235U Neutron Cross Section and Gamma Ray Production for ENDF/B-V written by M. R. Bhat and published by . This book was released on 1980 with total page 76 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Data Formats and Procedures for the ENDF Neutron Cross Section Library by : Henry C. Honeck
Download or read book Data Formats and Procedures for the ENDF Neutron Cross Section Library written by Henry C. Honeck and published by . This book was released on 1971 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Program GROUPLE (version 79-1) by : Dermott Edward Cullen
Download or read book Program GROUPLE (version 79-1) written by Dermott Edward Cullen and published by . This book was released on 1980 with total page 76 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Endf/B Fission Product Decay Data by : P. F. Rose
Download or read book Endf/B Fission Product Decay Data written by P. F. Rose and published by . This book was released on 1977 with total page 424 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 1980 with total page 1056 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Proceedings written by and published by . This book was released on 1971 with total page 502 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis NEW ENDF/B-VII LIBRARY. by : P. OBLOZINSKY
Download or read book NEW ENDF/B-VII LIBRARY. written by P. OBLOZINSKY and published by . This book was released on 2006 with total page 7 pages. Available in PDF, EPUB and Kindle. Book excerpt: We describe the current status of work on the new version of the U.S. Evaluated Nuclear Data File, ENDF/B-VII. The library, organized into 14 sublibraries, has number of improvements and extensions. In particular, there are new neutron cross section standards, considerably improved neutron cross sections for actinides, entirely new fission product neutron cross sections, improved thermal neutron scattering sublibrary, new photonuclear sublibrary, improved charged particle cross section sublibraries and other. Preliminary results of integral data testing & validation are very encouraging and it is expected that ENDF/B-VII.0 will be officially released later in 2006.
Download or read book ENDF/B-IV Thermal Data Testing written by and published by . This book was released on 1976 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The Evaluated Nuclear Data File/Library B (ENDF/B) provides a computer-oriented reference set of evaluated neutron cross sections for thermal and fast reactor applications, photon interaction cross sections, and photon production data. The current evaluations span the energy range from 0 to 20 MeV. This paper presents ENDF/B-IV data testing results from seven organizations on seventeen thermal benchmark experiments. Development and testing of ENDF/B-IV is the latest contribution of the Cross Section Evaluation Group. The file is maintained at, and released through, the National Neutron Cross Section Center at Brookhaven National Laboratory. The ENDF/B-IV predictions for uranium systems are an improvement over ENDF/B-III. Recommendations include extending the benchmark experiments to plutonium, urania, thoria, and mixed oxide systems and preparing a revised library, ENDF/B-V.
Book Synopsis CROSS SECTION EVALUATIONS FOR ENDF/B-VII. by : M. HERMAN
Download or read book CROSS SECTION EVALUATIONS FOR ENDF/B-VII. written by M. HERMAN and published by . This book was released on 2006 with total page 21 pages. Available in PDF, EPUB and Kindle. Book excerpt: This is the final report of the work performed under the LANL contract on neutron cross section evaluations for ENDF/B-VII (April 2005-May 2006). The purpose of the contract was to ensure seamless integration of the LANL neutron cross section evaluations in the new ENDF/B-VII library. The following work was performed: (1) LANL evaluated data files submitted for inclusion in ENDF/B-VII were checked and, when necessary, formal formatting errors were corrected. As a consequence, ENDF checking codes, run on all LANL files, do not report any errors that would rise concern. (2) LANL dosimetry evaluations for {sup 191}Ir and {sup 193}Ir were completed to match ENDF requirements for the general purpose library suitable for transport calculations. A set of covariances for both isotopes is included in the ENDF files. (3) Library of fission products was assembled and successfully tested with ENDF checking codes, processed with NJOY-99.125 and simple MCNP calculations. (4) KALMAN code has been integrated with the EMPIRE system to allow estimation of covariances based on the combination of measurements and model calculations. Covariances were produced for 155,157-Gd and also for 6 remaining isotopes of Gd.
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 500 pages. Available in PDF, EPUB and Kindle. Book excerpt: