Evaluation of Neutron and Gamma-ray-production Cross Sections for Natural Iron (ENDF/B-V MAT 1326)

Evaluation of Neutron and Gamma-ray-production Cross Sections for Natural Iron (ENDF/B-V MAT 1326) PDF Author:
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Category :
Languages : en
Pages : 41

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Evaluation of Neutron and Gamma-ray-production Cross Sections for Natural Iron (ENDF/B-V MAT 1326)

Evaluation of Neutron and Gamma-ray-production Cross Sections for Natural Iron (ENDF/B-V MAT 1326) PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 41

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Evaluation of Neutron and Gamma-ray-production Cross Sections for Natural Iron (ENDF/B-V MAT 1326). [100 EV to 2. 2 MeV].

Evaluation of Neutron and Gamma-ray-production Cross Sections for Natural Iron (ENDF/B-V MAT 1326). [100 EV to 2. 2 MeV]. PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :

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The evaluation of neutron and gamma-ray-production cross sections for natural iron is considered. Improvements for ENDF/B-V MAT 1326 are described and graphically compared with the previous version. A summary of the previous version and a general description of the current status of the evaluation are also given. 25 figures.

Evaluation of Neutron and Gamma-ray-production Cross Sections for Natural Iron (ENDF/B-V MAT 1326).

Evaluation of Neutron and Gamma-ray-production Cross Sections for Natural Iron (ENDF/B-V MAT 1326). PDF Author:
Publisher:
ISBN:
Category : Cross sections (Nuclear physics)
Languages : en
Pages :

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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 PDF Author: M. R. Bhat
Publisher:
ISBN:
Category : Gamma rays
Languages : en
Pages : 80

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Neutron and Gamma Ray Production

Neutron and Gamma Ray Production PDF Author:
Publisher:
ISBN:
Category : Gamma ray sources
Languages : en
Pages : 64

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

Evaluation of 235 U Neutron Cross Section and Gamma Ray Production Data for ENDF/B-V PDF Author: M. R. Bhat
Publisher:
ISBN:
Category :
Languages : en
Pages : 65

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Calculation of Neutron and Gamma-ray Production Cross Sections for Calcium from 8 to 20 MeV.

Calculation of Neutron and Gamma-ray Production Cross Sections for Calcium from 8 to 20 MeV. PDF Author:
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ISBN:
Category :
Languages : en
Pages :

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Book Description
Nuclear model calculations used for the previous evaluation for calcium (ENDF/B-V MAT 1320) lacked the effects of precompound particle emission. Experimental information now available suggests that these effects are significant from 8 to 20 MeV. Results of new calculations made to include such effects in all reaction cross sections from 8 to 20 MeV are presented. The resulting data set was prepared in the ENDF/B-V format and is referred to as Material 4152 Modification V in the DNA cross-section library.

Evaluation of 235U neutron cross section and gamma ray production data for ENDF/B-V

Evaluation of 235U neutron cross section and gamma ray production data for ENDF/B-V PDF Author:
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Category :
Languages : en
Pages :

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Evaluation of 235U Neutron Cross Section and Gamma Ray Production Data for ENDF

Evaluation of 235U Neutron Cross Section and Gamma Ray Production Data for ENDF PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :

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A discussion is given of the evaluation of neutron and gamma ray production cross sections of 235U from 10−5 eV to 20 MeV and the parts contributed by the author. All available new data are included in this evaluation, and the procedures adopted to assess the experimental data and adopt a set of recommended values are described. 22 figures, 10 tables.

Neutron Cross Sections and Technology

Neutron Cross Sections and Technology PDF Author: David T. Goldman
Publisher:
ISBN:
Category : Neutron cross sections
Languages : en
Pages : 730

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