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


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.




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


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.




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


Book Description

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.




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


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].


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.




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


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.


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).




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


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).







Neutron Cross Sections


Book Description

Neutron Cross Sections, Volume 2: Neutron Cross Section Curves presents data for total reaction cross sections and related fission parameters as a function of incident-neutron energy. This book covers energy range from 0.01 eV to 200 MeV to exclude crystalline and magnetic effects for slow neutrons and relativistic effects for high energy neutrons. The data in this volume are grouped into sections corresponding to the element of the target nucleus in the neutron-induced reaction. These sections are ordered in increasing atomic number. Within a section, graphical data are presented for the natural element followed by the isotopes of that element in order of increasing atomic mass. A list of the reaction types is provided at the end of each section. This book also provides graphical section, wherein each graphical page is annotated on the outer edge with a symbol for an element or isotope followed by the list of the cross section data for that element or isotope. The data plotted in the graphical section are tagged by a mnemonic consisting of year, laboratory, and author's last name. This tag can be used to find the corresponding reference on the bibliographic pages.