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Languages : en
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Book Description
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.
V(n, X. Gamma.) Reaction Cross Section for Incident Neutron Energies Between 0. 2 and 20. 0 MeV.
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Category :
Languages : en
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Book Description
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.
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
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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Category : Cross sections (Nuclear physics)
Languages : en
Pages : 57
Book Description
Publisher:
ISBN:
Category : Cross sections (Nuclear physics)
Languages : en
Pages : 57
Book Description
Cr(n, X$gamma$) Reaction Cross Section for Incident Neutron Energies Between 0.2 and 20.0 MeV.
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Languages : en
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Book Description
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).
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Category :
Languages : en
Pages :
Book Description
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).
Mn(n, X. Gamma.) Reaction Cross Section for Incident Neutron Energies Between 0. 2 and 20. 0 MeV.
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Languages : en
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Book Description
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.
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Category :
Languages : en
Pages :
Book Description
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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Category :
Languages : en
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Book Description
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).
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Category :
Languages : en
Pages :
Book Description
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).
Mo(n, X$gamma$) Reaction Cross Section for Incident Neutron Energies Between 0.2 and 20.0 MeV.
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Category :
Languages : en
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Book Description
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).
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ISBN:
Category :
Languages : en
Pages :
Book Description
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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Category :
Languages : en
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Languages : en
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Book Description
Au(n, X$gamma$) Reaction Cross Section for Incident Neutron Energies Between 0.2 and 20.0 MeV.
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Category :
Languages : en
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Category :
Languages : en
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Book Description
Ti(n, X. Gamma.) Reaction Cross Section for Incident Neutron Energies Between 0. 3 and 20. 0 MeV.
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Languages : en
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Book Description
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.
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Languages : en
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Book Description
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.
O(n, X. Gamma.) Reaction Cross Section for Incident Neutron Energies Between 6. 5 and 20. 0 MeV. [Yield].
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Category :
Languages : en
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Book Description
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.
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Category :
Languages : en
Pages :
Book Description
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.