Abstract
The results for Problems 5 and 6 of the NEACRP code comparison as submitted by six participating countries are presented in summary. These problems concentrate on the prediction of the neutron and gamma-ray sources arising in fuel after a specified irradiation, the fuel being uranium oxide for problem 5 and a mixture of uranium and plutonium oxides for problem 6. In both problems the predicted neutron sources are in good agreement for all participants. For gamma-rays however there are differences, largely due to the omission of bremstrahlung in some calculations. This discrepancy occurs at low energies and is not significant for shielding calculations, although it would be important for predicting heating rates in some circumstances.
Citation Formats
Locke, H F.
NEACRP comparison of codes for the radiation protection assessment of transportation packages. Solutions to problems 5 and 6.
NEA: N. p.,
1992.
Web.
Locke, H F.
NEACRP comparison of codes for the radiation protection assessment of transportation packages. Solutions to problems 5 and 6.
NEA.
Locke, H F.
1992.
"NEACRP comparison of codes for the radiation protection assessment of transportation packages. Solutions to problems 5 and 6."
NEA.
@misc{etde_10153299,
title = {NEACRP comparison of codes for the radiation protection assessment of transportation packages. Solutions to problems 5 and 6}
author = {Locke, H F}
abstractNote = {The results for Problems 5 and 6 of the NEACRP code comparison as submitted by six participating countries are presented in summary. These problems concentrate on the prediction of the neutron and gamma-ray sources arising in fuel after a specified irradiation, the fuel being uranium oxide for problem 5 and a mixture of uranium and plutonium oxides for problem 6. In both problems the predicted neutron sources are in good agreement for all participants. For gamma-rays however there are differences, largely due to the omission of bremstrahlung in some calculations. This discrepancy occurs at low energies and is not significant for shielding calculations, although it would be important for predicting heating rates in some circumstances.}
place = {NEA}
year = {1992}
month = {Mar}
}
title = {NEACRP comparison of codes for the radiation protection assessment of transportation packages. Solutions to problems 5 and 6}
author = {Locke, H F}
abstractNote = {The results for Problems 5 and 6 of the NEACRP code comparison as submitted by six participating countries are presented in summary. These problems concentrate on the prediction of the neutron and gamma-ray sources arising in fuel after a specified irradiation, the fuel being uranium oxide for problem 5 and a mixture of uranium and plutonium oxides for problem 6. In both problems the predicted neutron sources are in good agreement for all participants. For gamma-rays however there are differences, largely due to the omission of bremstrahlung in some calculations. This discrepancy occurs at low energies and is not significant for shielding calculations, although it would be important for predicting heating rates in some circumstances.}
place = {NEA}
year = {1992}
month = {Mar}
}