Mn(n, X. Gamma.) Reaction Cross Section for Incident Neutron Energies Between 0. 2 and 20. 0 MeV.

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Book Synopsis Mn(n, X. Gamma.) Reaction Cross Section for Incident Neutron Energies Between 0. 2 and 20. 0 MeV. by :

Download or read book Mn(n, X. Gamma.) Reaction Cross Section for Incident Neutron Energies Between 0. 2 and 20. 0 MeV. written by and published by . This book was released on 1976 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Differential cross sections for the neutron-induced gamma-ray production from natural manganese were measured for incident neutron energies between 0.2 and 20.0 MeV. The Oak Ridge Electron Linear Accelerator (ORELA) was used to provide the neutrons, and a NaI spectrometer, to detect the gamma rays at 125°. The data presented are the double differential cross section, d2sigma/d.cap omega.dE, for gamma-ray energies between 0.22 and 10.6 MeV for coarse intervals in incident neutron energy. The integrated yield of gamma rays of energies greater than 220 keV with higher resolution in the neutron energy is also presented. The experimental results are compared with the Evaluated Neutron Data Files (ENDF). 24 figures, 21 tables.

Cu(n, X$gamma$) Reaction Cross Section for Incident Neutron Energies Between 0.2 and 20.0 MeV.

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Book Synopsis Cu(n, X$gamma$) Reaction Cross Section for Incident Neutron Energies Between 0.2 and 20.0 MeV. by :

Download or read book Cu(n, X$gamma$) Reaction Cross Section for Incident Neutron Energies Between 0.2 and 20.0 MeV. written by and published by . This book was released on 1976 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Differential cross sections for the neutron-induced gamma-ray production from copper have been measured for incident neutron energies between 0.2 and 20.0 MeV. The Oak Ridge Linear Accelerator (ORELA) was used to provide the neutrons and a NaI spectrometer to detect the gamma rays at 125$sup 0$. The data presented are the doubly differential cross section, d$sup 2$sigma/d$Omega$dE, for gamma-ray energies between 0.3 and 10.6 MeV for coarse intervals in incident neutron energy. The integrated yield of gamma rays of energies greater than 300 keV with higher resolution in the neutron energy is also presented. The experimental results are compared with previous measurements made at ORELA and with the Evaluated Neutron Data File (ENDF/B-IV, MAT 1295). 41 figures, cross section tables. (auth).

V(n, X. Gamma.) Reaction Cross Section for Incident Neutron Energies Between 0. 2 and 20. 0 MeV.

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Book Synopsis V(n, X. Gamma.) Reaction Cross Section for Incident Neutron Energies Between 0. 2 and 20. 0 MeV. by :

Download or read book V(n, X. Gamma.) Reaction Cross Section for Incident Neutron Energies Between 0. 2 and 20. 0 MeV. written by and published by . This book was released on 1976 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Differential cross sections for the neutron-induced gamma-ray production from natural vanadium have been measured for incident neutron energies between 0.2 and 20.0 MeV. The Oak Ridge Linear Accelerator (ORELA) was used to provide the neutrons and a NaI spectrometer to detect the gamma rays at 125°. The data presented are the double differential cross section, d2sigma/d.cap omega.dE, for gamma-ray energies between 0.3 and 10.6 MeV for coarse intervals in incident neutron energy. The integrated yield of gamma rays of energies greater than 300 keV and higher resolution in the neutron energy is also presented. The experimental results are compared with the Evaluated Neutron Data Files (ENDF). 24 figures.

The Ti(n, X[gamma]) Reaction Cross Section for Incident Neutron Energies Between 0.3 and 20.0 MeV

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ISBN 13 :
Total Pages : 57 pages
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Book Synopsis The Ti(n, X[gamma]) Reaction Cross Section for Incident Neutron Energies Between 0.3 and 20.0 MeV by :

Download or read book The Ti(n, X[gamma]) Reaction Cross Section for Incident Neutron Energies Between 0.3 and 20.0 MeV written by and published by . This book was released on 1979 with total page 57 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Mo(n, X$gamma$) Reaction Cross Section for Incident Neutron Energies Between 0.2 and 20.0 MeV.

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ISBN 13 :
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Book Synopsis Mo(n, X$gamma$) Reaction Cross Section for Incident Neutron Energies Between 0.2 and 20.0 MeV. by :

Download or read book Mo(n, X$gamma$) Reaction Cross Section for Incident Neutron Energies Between 0.2 and 20.0 MeV. written by and published by . This book was released on 1975 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Differential cross sections for the neutron-induced gamma-ray production from natural molybdenum have been measured for incident neutron energies between 0.2 and 20.0 MeV. The Oak Ridge Linear Accelerator (ORELA) was used to provide the neutrons and a NaI spectrometer to detect the gamma rays at 125$sup 0$. The data presented are the double differential cross section, d$sup 2$sigma/ d$Omega$dE, for gamma-ray energies between 0.3 and 10.6 MeV for coarse intervals in incident neutron energy. The integrated yield of gamma rays of energies greater than 300 keV and higher resolution in the neutron energy is also presented. The experimental results are compared with the Evaluated Neutron Data Files (ENDF). 24 figures, data tables. (auth).

Nb(n, X$gamma$) Reaction Cross Section for Incident Neutron Energies Between 0.65 and 20.0 MeV.

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Book Synopsis Nb(n, X$gamma$) Reaction Cross Section for Incident Neutron Energies Between 0.65 and 20.0 MeV. by :

Download or read book Nb(n, X$gamma$) Reaction Cross Section for Incident Neutron Energies Between 0.65 and 20.0 MeV. written by and published by . This book was released on 1975 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Cr(n, X$gamma$) Reaction Cross Section for Incident Neutron Energies Between 0.2 and 20.0 MeV.

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Book Synopsis Cr(n, X$gamma$) Reaction Cross Section for Incident Neutron Energies Between 0.2 and 20.0 MeV. by :

Download or read book Cr(n, X$gamma$) Reaction Cross Section for Incident Neutron Energies Between 0.2 and 20.0 MeV. written by and published by . This book was released on 1976 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Differential cross sections for the neutron-induced gamma-ray production from natural chromium have been measured for incident neutron energies between 0.2 and 20.0 MeV. The Oak Ridge Linear Accelerator (ORELA) was used to provide the neutrons and a NaI spectrometer to detect the gamma rays at the laboratory angle of 125$sup 0$. The data presented are the double differential cross section, d$sup 2$sigma/d$Omega$dE, for gamma-ray energies between 0.3 and 10.6 MeV for coarse intervals in incident neutron energy. The integrated yield of gamma rays of energies greater than 300 keV and higher resolution in the neutron energy is also presented. The experimental results are compared with the Evaluated Neutron Data Files (ENDF). 23 figures, cross section tables (auth).

Au(n, X$gamma$) Reaction Cross Section for Incident Neutron Energies Between 0.2 and 20.0 MeV.

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ISBN 13 :
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Book Synopsis Au(n, X$gamma$) Reaction Cross Section for Incident Neutron Energies Between 0.2 and 20.0 MeV. by :

Download or read book Au(n, X$gamma$) Reaction Cross Section for Incident Neutron Energies Between 0.2 and 20.0 MeV. written by and published by . This book was released on 1975 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

O(n, X. Gamma.) Reaction Cross Section for Incident Neutron Energies Between 6. 5 and 20. 0 MeV. [Yield].

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Book Synopsis O(n, X. Gamma.) Reaction Cross Section for Incident Neutron Energies Between 6. 5 and 20. 0 MeV. [Yield]. by :

Download or read book O(n, X. Gamma.) Reaction Cross Section for Incident Neutron Energies Between 6. 5 and 20. 0 MeV. [Yield]. written by and published by . This book was released on 1979 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Differential cross sections for the neutron-induced gamma-ray production from oxygen were measured for incident neutron energies between 6.5 and 20.0 MeV. The Oak Ridge Electron Linear Accelerator (ORELA) was used to provide the neutrons and a NaI spectrometer to detect the gamma rays at 125°. The data presented are the double differential cross section, d2sigma/d.cap omega.dE, for gamma-ray energies between 1.6 and 10.6 MeV for coarse intervals in incident neutron energy. The integrated yield for gamma rays of energies greater than 1.6 MeV with higher resolution in the neutron energy is also presented. The experimental results are compared with the Evaluated Nuclear Data File (ENDF). 34 references.

Ti(n, X. Gamma.) Reaction Cross Section for Incident Neutron Energies Between 0. 3 and 20. 0 MeV.

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Book Synopsis Ti(n, X. Gamma.) Reaction Cross Section for Incident Neutron Energies Between 0. 3 and 20. 0 MeV. by :

Download or read book Ti(n, X. Gamma.) Reaction Cross Section for Incident Neutron Energies Between 0. 3 and 20. 0 MeV. written by and published by . This book was released on 1978 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Differential cross sections for the neutron-induced gamma-ray production from natural titanium were measured for incident neutron energies between 0.3 and 20.0 MeV. The Oak Ridge Electron Linear Accelerator (ORELA) was used to provide the neutrons, and a NaI spectrometer, to detect the gamma rays at 125°. The data presented are the double differential cross section, d2sigma/d.cap omega.dE, for gamma-ray energies between 0.3 and 10.6 MeV for coarse intervals in incident neutron energy. The integrated yield of gamma rays of energies greater than 300 keV with higher resolution in the neutron energy is also presented. The experimental results are compared with the Evaluated Nuclear Data Files (ENDF). 22 figures, 20 tables.

Th(n, X. Gamma.) Reaction Cross Section for Incident Neutron Energies Between 0. 3 and 20. 0 MeV. [. Gamma. Spectra, Excitation Functions].

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Book Synopsis Th(n, X. Gamma.) Reaction Cross Section for Incident Neutron Energies Between 0. 3 and 20. 0 MeV. [. Gamma. Spectra, Excitation Functions]. by :

Download or read book Th(n, X. Gamma.) Reaction Cross Section for Incident Neutron Energies Between 0. 3 and 20. 0 MeV. [. Gamma. Spectra, Excitation Functions]. written by and published by . This book was released on 1979 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Differential cross sections for the neutron-induced gamma-ray production from thorium were measured for incident neutron energies between 0.3 and 20.0 MeV. The Oak Ridge Electron Linear Accelerator (ORELA) was used to provide the neutrons, and a NaI spectrometer, to detect the gamma rays at 125/sup 0/. The data presented are the double differential cross section, d/sup 2/sigma/d.cap omega.dE, for gamma-ray energies between 0.3 and 10.6 MeV for coarse intervals in incident neutron energy. The integrated yield of gamma rays of energies greater than 300 keV with higher resolution in the neutron energy is also presented. 23 figures, 21 tables.

The TH(N,XY[gamma]) Reaction Cross Section for Incident Neutron Energies Between 0.3 and 20.0 MeV

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ISBN 13 :
Total Pages : 52 pages
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Book Synopsis The TH(N,XY[gamma]) Reaction Cross Section for Incident Neutron Energies Between 0.3 and 20.0 MeV by :

Download or read book The TH(N,XY[gamma]) Reaction Cross Section for Incident Neutron Energies Between 0.3 and 20.0 MeV written by and published by . This book was released on 1979 with total page 52 pages. Available in PDF, EPUB and Kindle. Book excerpt:

The Na(n,xY) Reaction Cross Section for Incident Neutron Energies Between 0.2 and 20.0 MeV

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ISBN 13 :
Total Pages : 67 pages
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Book Synopsis The Na(n,xY) Reaction Cross Section for Incident Neutron Energies Between 0.2 and 20.0 MeV by : Duane Clark Larson

Download or read book The Na(n,xY) Reaction Cross Section for Incident Neutron Energies Between 0.2 and 20.0 MeV written by Duane Clark Larson and published by . This book was released on 1978 with total page 67 pages. Available in PDF, EPUB and Kindle. Book excerpt:

The Ti(n,x) Reaction Cross Section for Incident Neutron Energies Between 0.3 and 20.0 MeV

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Total Pages : 52 pages
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Book Synopsis The Ti(n,x) Reaction Cross Section for Incident Neutron Energies Between 0.3 and 20.0 MeV by : G. L. Morgan

Download or read book The Ti(n,x) Reaction Cross Section for Incident Neutron Energies Between 0.3 and 20.0 MeV written by G. L. Morgan and published by . This book was released on 1978 with total page 52 pages. Available in PDF, EPUB and Kindle. Book excerpt:

The Ti(n,xγ) Reaction Cross Section for Incident Neutron Energies Between 0.3 and 20.0 MeV

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Total Pages : 0 pages
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Book Synopsis The Ti(n,xγ) Reaction Cross Section for Incident Neutron Energies Between 0.3 and 20.0 MeV by : G. L. Morgan

Download or read book The Ti(n,xγ) Reaction Cross Section for Incident Neutron Energies Between 0.3 and 20.0 MeV written by G. L. Morgan and published by . This book was released on 1978 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Gamma-ray Production Cross Sections for the 16O(n,x[gamma]) Reaction from 6.35- to 16.52-MeV Neutron Energy

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ISBN 13 :
Total Pages : 42 pages
Book Rating : 4.:/5 (13 download)

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Book Synopsis Gamma-ray Production Cross Sections for the 16O(n,x[gamma]) Reaction from 6.35- to 16.52-MeV Neutron Energy by : V. J. Orphan

Download or read book Gamma-ray Production Cross Sections for the 16O(n,x[gamma]) Reaction from 6.35- to 16.52-MeV Neutron Energy written by V. J. Orphan and published by . This book was released on 1970 with total page 42 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Analysis of Fe(n, X[gamma] Cross Sections Using the TNG Nuclear Reaction Model Code

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ISBN 13 :
Total Pages : 27 pages
Book Rating : 4.:/5 (873 download)

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Book Synopsis Analysis of Fe(n, X[gamma] Cross Sections Using the TNG Nuclear Reaction Model Code by :

Download or read book Analysis of Fe(n, X[gamma] Cross Sections Using the TNG Nuclear Reaction Model Code written by and published by . This book was released on 1993 with total page 27 pages. Available in PDF, EPUB and Kindle. Book excerpt: Theoretical gamma ray cross sections have been calculated using a nuclear reaction model code. These are compared to experimental gamma ray production cross sections obtained from neutron interactions with [sup 56]Fe at incident neutron energies of 1 to 40 MeV. The optical model and nuclear level density parameters in the code have been varied to affect a close agreement between calculations and the data. Present analyses, which focus on incident neutron energies between 17 and 40 MeV, display somewhat better agreement than those previously reported.