Publisher
Springer Science and Business Media LLC
Subject
Nuclear Energy and Engineering,Nuclear and High Energy Physics
Reference29 articles.
1. N.Z. Cho, G.S. Lee, C.J. Park, Fusion of method of characteristics and nodal method for 3-d whole-core transport calculation. Trans. Am. Nucl. Soc. 87, 322 (2002)
2. H. G. Joo, J. Y. Cho, K. S. Kim et al, Methods and performance of a three dimensional whole-core transport code DeCART. PHYSOR 2004—The Physics of Fuel Cycles and Advanced Nuclear Systems, Chicago, Illinois, US. (2004)
3. J.Y. Cho, H.G. Joo, Solution of the C5G7MOX benchmark three-dimensional extension problems by the DeCART direct whole core calculation code. Prog. Nucl. Energy 48, 456 (2006). https://doi.org/10.1016/j.pnucene.2006.01.006
4. Y.S. Jung, C.B. Shim, C.H. Lim et al., Practical numerical reactor employing direct whole core neutron transport and subchannel thermal/hydraulic solvers. Ann. Nucl. Energy 62, 357 (2013). https://doi.org/10.1016/j.anucene.2013.06.031
5. B. Collins, S. Stimpson, B.W. Kelley et al., Stability and accuracy of 3D neutron transport simulations using the 2D/1D method in MPACT. J. Comput. Phys. 326, 612 (2016). https://doi.org/10.1016/j.jcp.2016.08.022
Cited by
7 articles.
订阅此论文施引文献
订阅此论文施引文献,注册后可以免费订阅5篇论文的施引文献,订阅后可以查看论文全部施引文献