TY - JOUR
T1 - Phonon parameters fitting for the simulated Thermal-Neutron scattering cross section of H in ZrHx using Unified Monte Carlo method
AU - Wang, Lipeng
AU - Wan, Chenghui
AU - Cao, Liangzhi
AU - Wu, Hongchun
AU - Sjöstrand, H.
N1 - Publisher Copyright:
© 2020 Elsevier Ltd
PY - 2021/2
Y1 - 2021/2
N2 - Thermal-motion behavior of the neutron is characterized by the neutron thermal-scattering cross sections. The thermal-scattering cross sections depend on the Thermal Scattering Laws (TSL) tabulated in terms of S(α,β), which is usually generated by the LEAPR module of NJOY code, using corresponding Phonon Density Of States (PDOS). The ZrHx is a good moderator because of its large fraction of H, hence it is widely used in the nuclear technology. However, the S(α,β) uncertainties of H in ZrHx has not been reported yet. Therefore, a general methodology is proposed in this paper to produce such a covariance matrix-associated to a semi-empirical phonon model. This is accomplished by fitting the computer-simulated scattering data against experimental data using the Unified Monte Carlo (UMC) method. Two TRIGA reactor benchmarks have been analyzed for keff uncertainty from TSL of H in ZrHx. It can be observed that after fitting, the keff error decreased with smaller uncertainty.
AB - Thermal-motion behavior of the neutron is characterized by the neutron thermal-scattering cross sections. The thermal-scattering cross sections depend on the Thermal Scattering Laws (TSL) tabulated in terms of S(α,β), which is usually generated by the LEAPR module of NJOY code, using corresponding Phonon Density Of States (PDOS). The ZrHx is a good moderator because of its large fraction of H, hence it is widely used in the nuclear technology. However, the S(α,β) uncertainties of H in ZrHx has not been reported yet. Therefore, a general methodology is proposed in this paper to produce such a covariance matrix-associated to a semi-empirical phonon model. This is accomplished by fitting the computer-simulated scattering data against experimental data using the Unified Monte Carlo (UMC) method. Two TRIGA reactor benchmarks have been analyzed for keff uncertainty from TSL of H in ZrHx. It can be observed that after fitting, the keff error decreased with smaller uncertainty.
KW - TSLs covariance
KW - Thermal neutron scattering
KW - Unified Monte Carlo Method
KW - ZrHx
UR - https://www.scopus.com/pages/publications/85092702774
U2 - 10.1016/j.anucene.2020.107920
DO - 10.1016/j.anucene.2020.107920
M3 - 文章
AN - SCOPUS:85092702774
SN - 0306-4549
VL - 151
JO - Annals of Nuclear Energy
JF - Annals of Nuclear Energy
M1 - 107920
ER -