TY - JOUR
T1 - NAPTH
T2 - Neutronics analysis code system for the fusion-fission hybrid reactor with pressure tube type blanket
AU - Zu, Tiejun
AU - Wu, Hongchun
AU - Zheng, Youqi
AU - Cao, Liangzhi
AU - Yang, Chao
PY - 2013/3
Y1 - 2013/3
N2 - The fusion-fission hybrid reactor is considered as a potential path to the early application of fusion energy. A new concept with pressure tube type blanket has recently been proposed for a feasible hybrid reactor. In this paper, a code system for the neutronics analysis of the pressure tube type hybrid reactor is developed based on the two-step calculation scheme: the few-group homogeneous constant calculation and the full blanket calculation. The few-group homogeneous constants are calculated using the lattice code DRAGON4. The blanket transport calculation is performed by the multigroup Monte Carlo code. A link procedure for fitting the cross sections is developed between these two steps. An additional procedure is developed to calculate the burnup, power distribution, energy multiplication factor, tritium breeding ratio and neutron multiplication factor. From some numerical results, it is found that the code system NAPTH is reliable and exhibits good calculation efficiency. It can be used for the conceptual design of the pressure tube type hybrid reactor with precise geometry.
AB - The fusion-fission hybrid reactor is considered as a potential path to the early application of fusion energy. A new concept with pressure tube type blanket has recently been proposed for a feasible hybrid reactor. In this paper, a code system for the neutronics analysis of the pressure tube type hybrid reactor is developed based on the two-step calculation scheme: the few-group homogeneous constant calculation and the full blanket calculation. The few-group homogeneous constants are calculated using the lattice code DRAGON4. The blanket transport calculation is performed by the multigroup Monte Carlo code. A link procedure for fitting the cross sections is developed between these two steps. An additional procedure is developed to calculate the burnup, power distribution, energy multiplication factor, tritium breeding ratio and neutron multiplication factor. From some numerical results, it is found that the code system NAPTH is reliable and exhibits good calculation efficiency. It can be used for the conceptual design of the pressure tube type hybrid reactor with precise geometry.
KW - Energy multiplication factor
KW - Fusion-fission hybrid reactor
KW - Neutronics analysis
KW - Pressure tube
KW - Tritium breeding ratio
UR - https://www.scopus.com/pages/publications/84875217125
U2 - 10.1016/j.fusengdes.2013.02.014
DO - 10.1016/j.fusengdes.2013.02.014
M3 - 文章
AN - SCOPUS:84875217125
SN - 0920-3796
VL - 88
SP - 170
EP - 176
JO - Fusion Engineering and Design
JF - Fusion Engineering and Design
IS - 3
ER -