代表性论文专著
【1】He D*, Li Y, Pan Q, Liu X. Development of a Predictor-Corrector Quasi-Static Transient Fission Matrix combination method for the neutronics transient simulation[J]. Nuclear Engineering and Design, 2024,424:113301.
【2】Li Y, He D*, Pan Q, et al. Development and verification of the transient fission matrix combination method for the efficient neutron kinetic simulations[J]. Progress in Nuclear Energy, 2024, 173: 105265.
【3】He D*, Gao R, Li H, Pan Q, Liu X. The development of a high-performance combined fission matrix neutron transport and depletion coupled calculation[J]. Progress in nuclear energy, 2024,173:105260.
【4】He D*, Li Y, Zhang T, et al. The development of the combined fission matrix method in small advanced reactor design and optimization[J]. Annals of Nuclear Energy, 2023, 180: 109488.
【5】He D*, Walters W. Development of uncertainty analysis techniques for the fission matrix–based neutron transport code RAPID[J]. Nuclear Science and Engineering, 2022, 196(9): 1101-1113.
【6】He D, Zhang T, Liu X*. Theory and application of the functional expansion fission matrix[J]. Annals of Nuclear Energy, 2022, 179: 109401.
【7】He D, Walters W J*. A local fission matrix correction method for heterogeneous whole core transport with RAPID[J]. Annals of Nuclear Energy, 2019, 134: 263-272.
【8】He D, Walters W J*. A correction method for RAPID fission matrix calculations with control rod movement[J]. Progress in Nuclear Energy, 2020, 121: 103226.
【9】He D, Walters W J*. Fission matrix homogenization and iterative convergence in RAPID[J]. Progress in Nuclear Energy, 2020, 126: 103407.
【10】He D, Walters W J*. Development of RAPID transport calculation with heterogeneous temperature distribution[J]. Annals of Nuclear Energy, 2020, 148: 107685.