Abstract
In 1985 the Reactor Physics Committee of the Nuclear Energy Agency initiated an intercomparison of codes for the calculation of the performance of shielding for the transportation of spent reactor fuel. The results of the application of a range of codes to the prediction of the dose-rates in the four theoretical benchmarks set to examine the attenuation of radiation through a variety of cask geometries are presented in this report. The contributions from neutrons, fission product gamma-rays and secondary gamma-rays are tabulated separately, and grouped according to the type of method of calculation employed. A brief discussion is included for each set of results, and overall comparisons of the methods, codes, and nuclear data are made. A number of conclusions are drawn on the advantages and disadvantages of the various methods of calculation, based upon the results of their application to these four benchmark problems.
Citation Formats
Avery, A F, and Locke, H F.
NEACRP comparison of codes for the radiation protection assessment of transportation packages. Solutions to problems 1 - 4.
NEA: N. p.,
1992.
Web.
Avery, A F, & Locke, H F.
NEACRP comparison of codes for the radiation protection assessment of transportation packages. Solutions to problems 1 - 4.
NEA.
Avery, A F, and Locke, H F.
1992.
"NEACRP comparison of codes for the radiation protection assessment of transportation packages. Solutions to problems 1 - 4."
NEA.
@misc{etde_10153097,
title = {NEACRP comparison of codes for the radiation protection assessment of transportation packages. Solutions to problems 1 - 4}
author = {Avery, A F, and Locke, H F}
abstractNote = {In 1985 the Reactor Physics Committee of the Nuclear Energy Agency initiated an intercomparison of codes for the calculation of the performance of shielding for the transportation of spent reactor fuel. The results of the application of a range of codes to the prediction of the dose-rates in the four theoretical benchmarks set to examine the attenuation of radiation through a variety of cask geometries are presented in this report. The contributions from neutrons, fission product gamma-rays and secondary gamma-rays are tabulated separately, and grouped according to the type of method of calculation employed. A brief discussion is included for each set of results, and overall comparisons of the methods, codes, and nuclear data are made. A number of conclusions are drawn on the advantages and disadvantages of the various methods of calculation, based upon the results of their application to these four benchmark problems.}
place = {NEA}
year = {1992}
month = {Mar}
}
title = {NEACRP comparison of codes for the radiation protection assessment of transportation packages. Solutions to problems 1 - 4}
author = {Avery, A F, and Locke, H F}
abstractNote = {In 1985 the Reactor Physics Committee of the Nuclear Energy Agency initiated an intercomparison of codes for the calculation of the performance of shielding for the transportation of spent reactor fuel. The results of the application of a range of codes to the prediction of the dose-rates in the four theoretical benchmarks set to examine the attenuation of radiation through a variety of cask geometries are presented in this report. The contributions from neutrons, fission product gamma-rays and secondary gamma-rays are tabulated separately, and grouped according to the type of method of calculation employed. A brief discussion is included for each set of results, and overall comparisons of the methods, codes, and nuclear data are made. A number of conclusions are drawn on the advantages and disadvantages of the various methods of calculation, based upon the results of their application to these four benchmark problems.}
place = {NEA}
year = {1992}
month = {Mar}
}