ENDF/B Neutron Cross-section Data for Natural Helium (ENDF-125)

ENDF/B Neutron Cross-section Data for Natural Helium (ENDF-125)
Title ENDF/B Neutron Cross-section Data for Natural Helium (ENDF-125) PDF eBook
Author E. M. Pennington
Publisher
Pages 36
Release 1968
Genre Cross sections (Nuclear physics)
ISBN

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Evaluation of 235U Neutron Cross Section and Gamma Ray Production for ENDF/B-V

Evaluation of 235U Neutron Cross Section and Gamma Ray Production for ENDF/B-V
Title Evaluation of 235U Neutron Cross Section and Gamma Ray Production for ENDF/B-V PDF eBook
Author M. R. Bhat
Publisher
Pages 76
Release 1980
Genre Gamma rays
ISBN

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NBS Special Publication

NBS Special Publication
Title NBS Special Publication PDF eBook
Author
Publisher
Pages 1064
Release 1968
Genre Metric system
ISBN

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Nuclear Data for Science and Technology

Nuclear Data for Science and Technology
Title Nuclear Data for Science and Technology PDF eBook
Author Syed M. Qaim
Publisher Springer Science & Business Media
Pages 1041
Release 2012-12-06
Genre Science
ISBN 3642581137

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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.

ENDF/B

ENDF/B
Title ENDF/B PDF eBook
Author Henry C. Honeck
Publisher
Pages 118
Release 1967
Genre Nuclear reactors
ISBN

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ENDF-110

ENDF-110
Title ENDF-110 PDF eBook
Author Odelli Ozer
Publisher
Pages 150
Release 1971
Genre FORTRAN (Computer program language)
ISBN

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Publications

Publications
Title Publications PDF eBook
Author United States. National Bureau of Standards
Publisher
Pages 684
Release 1981
Genre Government publications
ISBN

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