ENDF-201, ENDF/B-VI Summary Documentation Supplement 1, ENDF/HE-VI Summary Documentation

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ISBN 13 :
Total Pages : 267 pages
Book Rating : 4.:/5 (893 download)

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Book Synopsis ENDF-201, ENDF/B-VI Summary Documentation Supplement 1, ENDF/HE-VI Summary Documentation by :

Download or read book ENDF-201, ENDF/B-VI Summary Documentation Supplement 1, ENDF/HE-VI Summary Documentation written by and published by . This book was released on 1996 with total page 267 pages. Available in PDF, EPUB and Kindle. Book excerpt: The National Nuclear Data Center (NNDC) provides coordination for and serves as the secretariat to the Cross Section Evaluation Working Group (CSWEG). CSEWG is responsible for the oversight of the ENDF/B Evaluated Nuclear Data File. All data are checked and reviewed by CSEWG, and the file is maintained at the NNDC. For a description of the ENDF/B-VI file, see the ENDF-102 Data Formats and Procedures for the Evaluated Nuclear Data File ENDF-6. The purpose of this addendum to the ENDF/B-VI Summary Documentation is to provide documentation of Releases 1, 2, 3, and 4 for the ENDF/B-VI and ENDF/HE-VI evaluated nuclear data libraries. These releases contain many new and revised evaluations for the neutron, photo-atomic interaction, radioactive decay data, spontaneous fission product yield, neutron-induced fission product yield, thermal neutron scattering, proton, deuteron, and triton sublibraries. The summaries have been extracted mainly from the ENDF/B-VI File 1 comments (MT = 451), which have been checked, edited, and may also include supplementary information. Some summaries have been provided by the evaluators in electronic format, while others are extracted from reports on the evaluations. All references have been checked and corrected, or updated where appropriate. A list of the laboratories which have contributed evaluations used in ENDF/B-VI is given.

ENDF-201 : ENDF/B-VI summary documentation, supplement 1 : ENDF/HE-VI summary documentation

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ISBN 13 :
Total Pages : 0 pages
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Book Synopsis ENDF-201 : ENDF/B-VI summary documentation, supplement 1 : ENDF/HE-VI summary documentation by : Victoria McLane

Download or read book ENDF-201 : ENDF/B-VI summary documentation, supplement 1 : ENDF/HE-VI summary documentation written by Victoria McLane and published by . This book was released on 1996 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:

ENDF-201

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ISBN 13 :
Total Pages : 473 pages
Book Rating : 4.:/5 (727 download)

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Book Synopsis ENDF-201 by :

Download or read book ENDF-201 written by and published by . This book was released on 1991 with total page 473 pages. Available in PDF, EPUB and Kindle. Book excerpt: Responsibility for oversight of the ENDF/B Evaluated Nuclear Data file lies with the Cross Section Evaluation Working Group (CSEWG), which is comprised of representatives from various governmental and industrial laboratories in the United States. Individual evaluations are provided by scientists at several US laboratories, including significant contributions by scientists from all over the world. In addition, ENDF/B-VI includes for the first time complete evaluations for three materials that were provided from laboratories outside the US. All data are checked and reviewed by CSEWG, and the data file is maintained and issued by the National Nuclear Data Center at Brookhaven National Laboratory. The previous version of the library, ENDF/B-V, was issued in 1979, and two revisions to the data file were provided in subsequent years, the latest occurring in 1981. A total of 75 new or extensively modified neutron sublibrary evaluations are included in ENDF/B-VI, and are summarized in this document. One incident proton sublibrary is described for Fe56. The remaining evaluations in ENDF/B-VI have been carried over from earlier versions of ENDF, and have been updated to reflect the new formats. The release of ENDF/B-VI was carried out between January and June of 1990, with groups of materials being released on ''tapes.'' Table 1 is an index to the evaluation summaries, and includes the material identification or MAT number, the responsible laboratory, and the ''tape'' number. These evaluations have been released without restrictions on their distribution or use.

ENDF-201 Supplement 1. ENDF/B-V. 2 Summary Documentation. Third Edition

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Total Pages : pages
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Book Synopsis ENDF-201 Supplement 1. ENDF/B-V. 2 Summary Documentation. Third Edition by :

Download or read book ENDF-201 Supplement 1. ENDF/B-V. 2 Summary Documentation. Third Edition written by and published by . This book was released on 1985 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The purpose of the present publication is to provide the summary documentation for Revision 2 of the General Purpose File of ENDF/B-V. Revision 2 embodies a series of updates for important materials in the ENDF/B-V libraries in advance of the more comprehensive changes that will accompany a complete version change to ENDF/B, Verison VI. The summary documents for the evaluations that were completely or extensively modified during Revision 2 are provided. Less extensive changes made to other evaluations are also documented. Modifications made to the fission energy release parameters for fissionable nuclei are described. Finally, a series of modifications made to the covariance files of the major fissionable nuclei, including cross correlation information, is summarized. (LEW).

ENDF-201, ENDF

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ISBN 13 :
Total Pages : 267 pages
Book Rating : 4.:/5 (684 download)

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Book Synopsis ENDF-201, ENDF by :

Download or read book ENDF-201, ENDF written by and published by . This book was released on 1996 with total page 267 pages. Available in PDF, EPUB and Kindle. Book excerpt: The National Nuclear Data Center (NNDC) provides coordination for and serves as the secretariat to the Cross Section Evaluation Working Group (CSWEG). CSEWG is responsible for the oversight of the ENDF/B Evaluated Nuclear Data File. All data are checked and reviewed by CSEWG, and the file is maintained at the NNDC. For a description of the ENDF/B-VI file, see the ENDF-102 Data Formats and Procedures for the Evaluated Nuclear Data File ENDF-6. The purpose of this addendum to the ENDF/B-VI Summary Documentation is to provide documentation of Releases 1, 2, 3, and 4 for the ENDF/B-VI and ENDF/HE-VI evaluated nuclear data libraries. These releases contain many new and revised evaluations for the neutron, photo-atomic interaction, radioactive decay data, spontaneous fission product yield, neutron-induced fission product yield, thermal neutron scattering, proton, deuteron, and triton sublibraries. The summaries have been extracted mainly from the ENDF/B-VI File 1 comments (MT = 451), which have been checked, edited, and may also include supplementary information. Some summaries have been provided by the evaluators in electronic format, while others are extracted from reports on the evaluations. All references have been checked and corrected, or updated where appropriate. A list of the laboratories which have contributed evaluations used in ENDF/B-VI is given.

ENDF-201 Supplement 1. ENDF

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Book Synopsis ENDF-201 Supplement 1. ENDF by :

Download or read book ENDF-201 Supplement 1. ENDF written by and published by . This book was released on 1985 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The purpose of the present publication is to provide the summary documentation for Revision 2 of the General Purpose File of ENDF/B-V. Revision 2 embodies a series of updates for important materials in the ENDF/B-V libraries in advance of the more comprehensive changes that will accompany a complete version change to ENDF/B, Verison VI. The summary documents for the evaluations that were completely or extensively modified during Revision 2 are provided. Less extensive changes made to other evaluations are also documented. Modifications made to the fission energy release parameters for fissionable nuclei are described. Finally, a series of modifications made to the covariance files of the major fissionable nuclei, including cross correlation information, is summarized. (LEW).

ENDF/B-VI Summary Documentation. Supplement I, ENDF.

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Book Synopsis ENDF/B-VI Summary Documentation. Supplement I, ENDF. by : Victoria McLane

Download or read book ENDF/B-VI Summary Documentation. Supplement I, ENDF. written by Victoria McLane and published by . This book was released on 1996 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

ENDF-201 Supplement I

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ISBN 13 :
Total Pages : 203 pages
Book Rating : 4.:/5 (13 download)

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Book Synopsis ENDF-201 Supplement I by : National Nuclear Data Center

Download or read book ENDF-201 Supplement I written by National Nuclear Data Center and published by . This book was released on 1985 with total page 203 pages. Available in PDF, EPUB and Kindle. Book excerpt:

ENDF/B-VI Summary Documentation

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ISBN 13 :
Total Pages : 473 pages
Book Rating : 4.:/5 (13 download)

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Book Synopsis ENDF/B-VI Summary Documentation by : P. F. Rose

Download or read book ENDF/B-VI Summary Documentation written by P. F. Rose and published by . This book was released on 1991 with total page 473 pages. Available in PDF, EPUB and Kindle. Book excerpt:

ENDF/B Summary Documentation

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Book Synopsis ENDF/B Summary Documentation by :

Download or read book ENDF/B Summary Documentation written by and published by . This book was released on 1979 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: This publication provides a localized source of descriptions for the evaluations contained in the ENDF/B Library. The summary documentation presented is intended to be a more detailed description than the (File 1) comments contained in the computer readable data files, but not so detailed as the formal reports describing each ENDF/B evaluation. The summary documentations were written by the CSEWB (Cross Section Evaluation Working Group) evaluators and compiled by NNDC (National Nuclear Data Center). This edition includes documentation for materials found on ENDF/B Version V tapes 501 to 516 (General Purpose File) excluding tape 504. ENDF/B-V also includes tapes containing partial evaluations for the Special Purpose Actinide (521, 522), Dosimetry (531), Activation (532), Gas Production (533), and Fission Product (541-546) files. The materials found on these tapes are documented elsewhere. Some of the evaluation descriptions in this report contain cross sections or energy level information. (RWR).

Experimental and analytical investigations on nuclear reactor safety, severe accident phenomena and severe accident mitigation of nuclear power plants

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Publisher : Frontiers Media SA
ISBN 13 : 2832513123
Total Pages : 226 pages
Book Rating : 4.8/5 (325 download)

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Book Synopsis Experimental and analytical investigations on nuclear reactor safety, severe accident phenomena and severe accident mitigation of nuclear power plants by : Yapei Zhang

Download or read book Experimental and analytical investigations on nuclear reactor safety, severe accident phenomena and severe accident mitigation of nuclear power plants written by Yapei Zhang and published by Frontiers Media SA. This book was released on 2023-02-02 with total page 226 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Proceedings of International Conference on Nuclear Data for Science and Technology

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ISBN 13 :
Total Pages : 880 pages
Book Rating : 4.3/5 (91 download)

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Book Synopsis Proceedings of International Conference on Nuclear Data for Science and Technology by : Keiichi Shibata

Download or read book Proceedings of International Conference on Nuclear Data for Science and Technology written by Keiichi Shibata and published by . This book was released on 2002 with total page 880 pages. Available in PDF, EPUB and Kindle. Book excerpt:

ENDF

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Book Synopsis ENDF by :

Download or read book ENDF written by and published by . This book was released on 1979 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The NJOY processing system was used to produce thermal reactor cross-section libraries from ENDF/B-IV, and -V evaluations for the fuel cycle codes EPRI-CELL and EPRI-CPM, for the continuous-energy Monte Carlo code MCNP, and for the Los Alamos discrete-ordinates transport codes. This consistent data source allowed the approximate methods (equivalence theory, B1, integral transport, P/sub L/-S/sub N/) to be compared with accurate Monte Carlo results. So far, this has resulted in improved methods for space-and-energy self-shielding in the resonance range (e.g., the NJOY flux calculator, epithermal disadvantage factors for EPRI-CELL, shielded elastic removal), it has shown why the newest ENDF-based libraries initially gave results worse than the old libraries, and it has pointed out problems for future study such as resonance interference effects at high burnup. Finally, the results are compared to various criticality benchmarks to evaluate the performance of ENDF/B-V for thermal reactor analysis and to establish the biases introduced by the approximate methods used in the fuel cycle codes. 3 tables.

Energy Research Abstracts

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ISBN 13 :
Total Pages : 716 pages
Book Rating : 4.3/5 (129 download)

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Book Synopsis Energy Research Abstracts by :

Download or read book Energy Research Abstracts written by and published by . This book was released on 1985 with total page 716 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Nuclear Data Needs for Generation IV Nuclear Energy Systems

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Publisher : World Scientific
ISBN 13 : 9812568301
Total Pages : 300 pages
Book Rating : 4.8/5 (125 download)

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Book Synopsis Nuclear Data Needs for Generation IV Nuclear Energy Systems by : P. Rullhusen

Download or read book Nuclear Data Needs for Generation IV Nuclear Energy Systems written by P. Rullhusen and published by World Scientific. This book was released on 2006 with total page 300 pages. Available in PDF, EPUB and Kindle. Book excerpt: This volume presents recent progress in the improvement of the nuclear database needed for the development of Generation IV nuclear energy systems.The Generation IV International Forum (GIF) identified six advanced concepts for sustainable nuclear energy production at competitive prices and with advanced safety, with special attention to nuclear non-proliferation and physical protection issues, minimization of long-lived radiotoxic waste, and optimum natural resource utilization System groups have been established for studying these concepts in detail, and nuclear data are an inherent part of these studies. This book reviews the work recently performed for the development of these systems.The contributions include an up-to-date overview of recent achievements in sensitivity analysis, model calculations, estimates of uncertainties, and the present status of nuclear databases with regard to their applications to Generation IV systems. In the workshop, special attention was given to the identification of nuclear data needs from sensitivity analysis of benchmark experiments and the treatment of uncertainties. The proceedings contain overviews of several experimental program and recent results of interest for the development of Generation IV systems.

Nuclear Data Needs For Generation Iv Nuclear Energy Systems - Proceedings Of The International Workshop

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Publisher : World Scientific
ISBN 13 : 9814477796
Total Pages : 300 pages
Book Rating : 4.8/5 (144 download)

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Book Synopsis Nuclear Data Needs For Generation Iv Nuclear Energy Systems - Proceedings Of The International Workshop by : Peter Rullhusen

Download or read book Nuclear Data Needs For Generation Iv Nuclear Energy Systems - Proceedings Of The International Workshop written by Peter Rullhusen and published by World Scientific. This book was released on 2006-05-08 with total page 300 pages. Available in PDF, EPUB and Kindle. Book excerpt: This volume presents recent progress in the improvement of the nuclear database needed for the development of Generation IV nuclear energy systems.The Generation IV International Forum (GIF) identified six advanced concepts for sustainable nuclear energy production at competitive prices and with advanced safety, with special attention to nuclear non-proliferation and physical protection issues, minimization of long-lived radiotoxic waste, and optimum natural resource utilization System groups have been established for studying these concepts in detail, and nuclear data are an inherent part of these studies. This book reviews the work recently performed for the development of these systems.The contributions include an up-to-date overview of recent achievements in sensitivity analysis, model calculations, estimates of uncertainties, and the present status of nuclear databases with regard to their applications to Generation IV systems. In the workshop, special attention was given to the identification of nuclear data needs from sensitivity analysis of benchmark experiments and the treatment of uncertainties. The proceedings contain overviews of several experimental program and recent results of interest for the development of Generation IV systems.

The Journal of the Korean Physical Society

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ISBN 13 :
Total Pages : 704 pages
Book Rating : 4.8/5 (151 download)

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Book Synopsis The Journal of the Korean Physical Society by :

Download or read book The Journal of the Korean Physical Society written by and published by . This book was released on 2006 with total page 704 pages. Available in PDF, EPUB and Kindle. Book excerpt: