Abstract
Uncertainties in delayed neutron summation calculations are evaluated with ENDF/B-VI for 50 fissioning systems. As the first step, uncertainty calculations are performed for the aggregate delayed neutron activity with the same approximate method as proposed previously for the decay heat uncertainty analyses. Typical uncertainty values are about 6-14% for {sup 238}U(F) and about 13-23% for {sup 243}Am(F) at cooling times 0.1-100 (s). These values are typically 2-3 times larger than those in decay heat at the same cooling times. For aggregate delayed neutron spectra, the uncertainties would be larger than those for the delayed neutron activity because much more information about the nuclear structure is still necessary. (author)
Citation Formats
Miyazono, T, Sagisaka, M, Ohta, H, Oyamatsu, K, and Tamaki, M.
Delayed neutron spectra and their uncertainties in fission product summation calculations.
Japan: N. p.,
1997.
Web.
Miyazono, T, Sagisaka, M, Ohta, H, Oyamatsu, K, & Tamaki, M.
Delayed neutron spectra and their uncertainties in fission product summation calculations.
Japan.
Miyazono, T, Sagisaka, M, Ohta, H, Oyamatsu, K, and Tamaki, M.
1997.
"Delayed neutron spectra and their uncertainties in fission product summation calculations."
Japan.
@misc{etde_544674,
title = {Delayed neutron spectra and their uncertainties in fission product summation calculations}
author = {Miyazono, T, Sagisaka, M, Ohta, H, Oyamatsu, K, and Tamaki, M}
abstractNote = {Uncertainties in delayed neutron summation calculations are evaluated with ENDF/B-VI for 50 fissioning systems. As the first step, uncertainty calculations are performed for the aggregate delayed neutron activity with the same approximate method as proposed previously for the decay heat uncertainty analyses. Typical uncertainty values are about 6-14% for {sup 238}U(F) and about 13-23% for {sup 243}Am(F) at cooling times 0.1-100 (s). These values are typically 2-3 times larger than those in decay heat at the same cooling times. For aggregate delayed neutron spectra, the uncertainties would be larger than those for the delayed neutron activity because much more information about the nuclear structure is still necessary. (author)}
place = {Japan}
year = {1997}
month = {Mar}
}
title = {Delayed neutron spectra and their uncertainties in fission product summation calculations}
author = {Miyazono, T, Sagisaka, M, Ohta, H, Oyamatsu, K, and Tamaki, M}
abstractNote = {Uncertainties in delayed neutron summation calculations are evaluated with ENDF/B-VI for 50 fissioning systems. As the first step, uncertainty calculations are performed for the aggregate delayed neutron activity with the same approximate method as proposed previously for the decay heat uncertainty analyses. Typical uncertainty values are about 6-14% for {sup 238}U(F) and about 13-23% for {sup 243}Am(F) at cooling times 0.1-100 (s). These values are typically 2-3 times larger than those in decay heat at the same cooling times. For aggregate delayed neutron spectra, the uncertainties would be larger than those for the delayed neutron activity because much more information about the nuclear structure is still necessary. (author)}
place = {Japan}
year = {1997}
month = {Mar}
}