TY - JOUR
T1 - Sensitivity and uncertainty analyses of a high temperature gas-cooled reactor by using a 44-group covariance library
AU - Hartanto, Donny
AU - Liem, Peng Hong
N1 - Publisher Copyright:
© 2020 Elsevier Ltd
PY - 2021/2
Y1 - 2021/2
N2 - Sensitivity and uncertainty analyses of the effective neutron multiplication factor (keff) were conducted for the High Temperature Engineering Test Reactor (HTTR) using the ENDF/B-VII.1 nuclear data and the 44-group covariance library provided in the Whisper-1.1. Amongst the criticality benchmark series, the fully-loaded core was selected and analyzed by using a continuous energy Monte Carlo code, MCNP6.2. The top-five positive sensitivity coefficients (+0.1–+0.03) were found to be U-235 (total nu and fission), C-12 (elastic), graphite S(a,b) (elastic and inelastic), while the top-five negative ones (−0.1–−0.003) were U-238 (n,gamma), U-235 (n,gamma), B-10 (n,alpha), C-12 (n,gamma) and Si-28 (n,gamma). The keff uncertainty originated from the nuclear data was calculated using the previously obtained sensitivity coefficients and the 44-group covariance library. In the present S/U analysis, we obtained the keff uncertainty of about 0.5%. The JENDL-4.0 and ENDF/B-VIII.0 nuclear data were also analyzed for comparison.
AB - Sensitivity and uncertainty analyses of the effective neutron multiplication factor (keff) were conducted for the High Temperature Engineering Test Reactor (HTTR) using the ENDF/B-VII.1 nuclear data and the 44-group covariance library provided in the Whisper-1.1. Amongst the criticality benchmark series, the fully-loaded core was selected and analyzed by using a continuous energy Monte Carlo code, MCNP6.2. The top-five positive sensitivity coefficients (+0.1–+0.03) were found to be U-235 (total nu and fission), C-12 (elastic), graphite S(a,b) (elastic and inelastic), while the top-five negative ones (−0.1–−0.003) were U-238 (n,gamma), U-235 (n,gamma), B-10 (n,alpha), C-12 (n,gamma) and Si-28 (n,gamma). The keff uncertainty originated from the nuclear data was calculated using the previously obtained sensitivity coefficients and the 44-group covariance library. In the present S/U analysis, we obtained the keff uncertainty of about 0.5%. The JENDL-4.0 and ENDF/B-VIII.0 nuclear data were also analyzed for comparison.
KW - ENDF/B-VII.1
KW - ENDF/B-VIII.0
KW - HTTR
KW - JENDL-4.0
KW - Sensitivity and Uncertainty
KW - Whisper-1.1 44-Group Covariance Library
UR - http://www.scopus.com/inward/record.url?scp=85094096424&partnerID=8YFLogxK
U2 - 10.1016/j.anucene.2020.107943
DO - 10.1016/j.anucene.2020.107943
M3 - Article
AN - SCOPUS:85094096424
SN - 0306-4549
VL - 151
JO - Annals of Nuclear Energy
JF - Annals of Nuclear Energy
M1 - 107943
ER -