TY - JOUR
T1 - Analysis of a neutronic experiment on a simulated mercury spoliation neutron target assembly bombarded by giga-electron-volt protons
AU - Maekawa, Fujio
AU - Meigo, Shin Ichiro
AU - Kasugai, Yoshimi
AU - Takada, Hiroshi
AU - Ino, Takashi
AU - Sato, Setsuo
AU - Jerde, Eric
AU - Glasgow, David
AU - Niita, Koji
AU - Nakashima, Hiroshi
AU - Oyama, Yukio
AU - Ikeda, Yujiro
AU - Watanabe, Noboru
AU - Hastings, Jerome
PY - 2005/5
Y1 - 2005/5
N2 - A neutronic benchmark experiment on a simulated spoliation neutron target assembly was conducted by using the Alternating Gradient Synchrotron at Brookhaven National Laboratory and was analyzed to investigate the prediction capability of Monte Carlo simulation codes used in neutronic designs of spoliation neutron sources. The target assembly consisting of a mercury target, a light water moderator, and a lead reflector was bombarded by 1.94-, 12-, and 24-GeV protons, and the fast neutron flux distributions around the target and the spectra of thermal neutrons leaking from the moderator were measured in the experiment. In this study, the Monte Carlo particle transport simulation codes NMTC/ JAM, MCNPX, and MCNP-4A with associated cross-section data in JENDL and LA-150 were verified based on benchmark analysis of the experiment. As a result, all the calculations predicted the measured quantities adequately; calculated integral fluxes of fast and thermal neutrons agreed approximately within ±40% with the experiments although the overall energy range encompassed more than 12 orders of magnitude. Accordingly, it was concluded that these simulation codes and cross-section data were adequate for neutronics designs of spoliation neutron sources.
AB - A neutronic benchmark experiment on a simulated spoliation neutron target assembly was conducted by using the Alternating Gradient Synchrotron at Brookhaven National Laboratory and was analyzed to investigate the prediction capability of Monte Carlo simulation codes used in neutronic designs of spoliation neutron sources. The target assembly consisting of a mercury target, a light water moderator, and a lead reflector was bombarded by 1.94-, 12-, and 24-GeV protons, and the fast neutron flux distributions around the target and the spectra of thermal neutrons leaking from the moderator were measured in the experiment. In this study, the Monte Carlo particle transport simulation codes NMTC/ JAM, MCNPX, and MCNP-4A with associated cross-section data in JENDL and LA-150 were verified based on benchmark analysis of the experiment. As a result, all the calculations predicted the measured quantities adequately; calculated integral fluxes of fast and thermal neutrons agreed approximately within ±40% with the experiments although the overall energy range encompassed more than 12 orders of magnitude. Accordingly, it was concluded that these simulation codes and cross-section data were adequate for neutronics designs of spoliation neutron sources.
UR - http://www.scopus.com/inward/record.url?scp=21044442681&partnerID=8YFLogxK
U2 - 10.13182/NSE05-A2504
DO - 10.13182/NSE05-A2504
M3 - Article
AN - SCOPUS:21044442681
SN - 0029-5639
VL - 150
SP - 99
EP - 108
JO - Nuclear Science and Engineering
JF - Nuclear Science and Engineering
IS - 1
ER -