Zobrazeno 1 - 10
of 14
pro vyhledávání: '"Donghao He"'
Publikováno v:
Frontiers in Energy Research, Vol 9 (2021)
The combined fission matrix theory is a recently-developed hybrid neutron transport method. It features high efficiency, fidelity, and resolution whole-core transport calculation. The theory is based on the assumption that the fission matrix element
Externí odkaz:
https://doaj.org/article/36f7f24126ce4db7b9a07d3df2e4277b
Autor:
HUI YU, YU ZHANG, JIN ZHAO, YUJIAN LIAO, ZHIYING HUANG, DONGHAO HE, LIN GU, HAI JIN, XIAOFEI LIAO, HAIKUN LIU, BINGSHENG HE, JIANHUI YUE
Publikováno v:
ACM Transactions on Architecture & Code Optimization; Dec2023, Vol. 20 Issue 4, p1-26, 26p
Publikováno v:
Springer Proceedings in Physics ISBN: 9789811988981
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::97a7054494d217694cc3bade4e23cc69
https://doi.org/10.1007/978-981-19-8899-8_52
https://doi.org/10.1007/978-981-19-8899-8_52
Publikováno v:
Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology.
This paper presents an implementation of the stiffness confinement method in the framework of the variational nodal method (VNM) to solve time-dependent pin resolved neutron transport equations. With frequency-transform, the time-dependent neutron tr
Publikováno v:
Annals of Nuclear Energy. 180:109488
Autor:
Donghao He, William J. Walters
Publikováno v:
Annals of Nuclear Energy. 134:263-272
The recently developed RAPID code uses a unique pre-calculated fission matrix method in order to solve the whole-core eigenvalue problem very quickly and accurately. However, in strongly heterogeneous cores, errors are introduced at the boundary betw
Publikováno v:
Annals of Nuclear Energy. 179:109401
Publikováno v:
Computer Physics Communications. 274:108290
Autor:
Donghao He1 donghaohe@sjtu.edu.cn, Walters, William2
Publikováno v:
Nuclear Science & Engineering. Sep2022, Vol. 196 Issue 9, p1101-1113. 13p.
Publikováno v:
Annals of Nuclear Energy. 158:108291
In this paper we report validation studies of the Monte Carlo code OpenMC by the ASTRA critical facility benchmark. A high-fidelity reactor model is built using the regular lattice coated fuel particle and the body centered cube pebble spheres repres