Precision Neutron Total Cross-Sectional Measurements for Natural Carbon at Reactor Neutron-Filtered Beams PDF Download
Are you looking for read ebook online? Search for your book and save it on your Kindle device, PC, phones or tablets. Download Precision Neutron Total Cross-Sectional Measurements for Natural Carbon at Reactor Neutron-Filtered Beams PDF full book. Access full book title Precision Neutron Total Cross-Sectional Measurements for Natural Carbon at Reactor Neutron-Filtered Beams by O. Gritzay. Download full books in PDF and EPUB format.
Author: O. Gritzay Publisher: ISBN: Category : Carbon Languages : en Pages : 7
Book Description
An experimental investigation of the total neutron cross section for natural carbon was made at Kyiv Research Reactor using neutron-filtered beams with energies 24, 59, and 148 keV. The intense neutron beams formed by composite neutron filters at reactor horizontal channels )had fluxes of about 106 to 107 neutron/cm2 s at the fixed neutron energies, which enabled us to measure the neutron cross sections with accuracy better than 1 %. Transmission method was used in these measurements. The results of the measurements are presented together with the analysis of the known previous experimental data and the evaluated nuclear data from ENDF libraries. Sample thickness dependence of the observed neutron cross section, measured at the 148-keV filter, has been detected which hypothetically may be connected with existence of a very strong resonance in the 13C neutron cross section in the energy range 119 to 157 keV.
Author: O. Gritzay Publisher: ISBN: Category : Carbon Languages : en Pages : 7
Book Description
An experimental investigation of the total neutron cross section for natural carbon was made at Kyiv Research Reactor using neutron-filtered beams with energies 24, 59, and 148 keV. The intense neutron beams formed by composite neutron filters at reactor horizontal channels )had fluxes of about 106 to 107 neutron/cm2 s at the fixed neutron energies, which enabled us to measure the neutron cross sections with accuracy better than 1 %. Transmission method was used in these measurements. The results of the measurements are presented together with the analysis of the known previous experimental data and the evaluated nuclear data from ENDF libraries. Sample thickness dependence of the observed neutron cross section, measured at the 148-keV filter, has been detected which hypothetically may be connected with existence of a very strong resonance in the 13C neutron cross section in the energy range 119 to 157 keV.
Author: David W. Vehar Publisher: ASTM International ISBN: Category : Science Languages : en Pages : 536
Book Description
"The latest edition of this popular ASTM series provides an extensive overview of the latest advances in reactor dosimetry. As operating nuclear power reactors have aged and continue to operate on extended operating licenses, new pressure vessel surveillance techniques have been required. Eastern European pressurized water reactors, especially those of the VVER-440 type, continue to have greater concerns about steel embrittlement, because of higher neutron radiation exposures than most Western European and US reactors. Accordingly, broader dosimetry studies are being made on the VVER reactors through retrospective dosimetry, ex-vessel dosimetry, and careful re-analysis of previously reported data."--Publisher's website.
Author: M. Kalos Publisher: ISBN: Category : Carbon Languages : en Pages : 30
Book Description
A tabulation is made of total and elastic scattering cross sections together with Legendre coefficients for elastic angular distributions for neutron scattering by carbon, in the range 0.33 to 18.0 Mev.
Author: Publisher: ISBN: Category : Languages : en Pages :
Book Description
Research progress is reported for the following projects: (1) the neutron total cross section of sodium near minimum, (2) $sup 238$U(n, $gamma$) measurements with Fe-filtered neutron TOF beams, (3) neutron capture and transmission measurements on $sup 101$Ru, $sup 102$Ru, $sup 104$Ru, $sup 145$Nd, and $sup 149$Sm, (4) capture cross section normalization and analysis of $sup 101$Ru, $sup 10$$sub 2$, $sup 104$Ru, $sup 145$Nd, $sup 149$Sm, (5) neutron capture and transmission experiments on $sup 95$Mo, $sup 97$Mo, $sup 133$Cs, and $sup 143$Nd, (6) capture cross section measurements of radioactive fission products, and (7) neutron capture and transmission data analysis system. (SDF).
Author: O. Gritzay
Author: O. Gritzay
Author: 
Author: 
Author: David W. Vehar
Author: M. Kalos
Author: David T. Goldman
Author: 
Author: William Raymond Bohl
Author: 
Author: