Neutronic simulation of China Experimental Fast Reactor start-up tests. Part I: SARAX code deterministic calculation
Tài liệu tham khảo
Chen, 2013, Measurement and analysis of CEFR safety and shim rod worth, At. Energy Sci. Technol., 47, 92
Choe, 2019, Verification and validation of STREAM/RAST-K for PWR analysis, Nucl. Eng. Technol., 51, 356, 10.1016/j.net.2018.10.004
Choi, 2017, Resonance treatment using pin-based pointwise energy slowing-down method, J. Comput. Phys., 330, 134, 10.1016/j.jcp.2016.11.007
Du, 2018, A hybrid method to generate few-group cross sections for fast reactor analysis, J. Nucl. Sci. Technol., 55, 931, 10.1080/00223131.2018.1452650
Du, 2019, Application of TULIP/STREAM code in 2-D fast reactor core neutronic analysis
Guo, 2019, Advanced method for neutronic simulation of control rods in sodium fast reactors: numerical and experimental validation, Ann. Nucl. Energy, 129, 90, 10.1016/j.anucene.2019.01.042
Huo, 2018
IAEA, 2012
IAEA, 2014
Ikegami, 2006
Jang, 2018, Validation of UNIST Monte Carlo code MCS for criticality safety analysis of pwr spent fuel pool and storage cask, Ann. Nucl. Energy, 114, 495, 10.1016/j.anucene.2017.12.054
Lee, 2017, MC2-3: multigroup cross section generation code for fast reactor analysis, Nucl. Sci. Eng., 187, 268, 10.1080/00295639.2017.1320893
Lu H.L., 2007. Nodal Methods for the Neutron Diffusion and Transport Equations in Triangular Meshes, Ph.D thesis, Xi’an Jiaotong University, July 2007 (in Chinese).
G. Rimpault, Algorithmic features of the ECCO cell code for treating heterogeneous fast reactor subassemblies, Proceedings of the International Topical Meeting on Reactor Physics and Computations; 1995 May 1–5; Portland (OR), USA.
Steven, 2006, Benchmarking ENDF/B-VII.0, Nucl. Data Sheets, 107, 3061, 10.1016/j.nds.2006.11.002
Tak, 2013, Design of ultra-long cycle fast reactor employing breed-and-burn strategy, Nucl. Technol., 183, 427, 10.13182/NT13-A19430
Tak, 2014, Optimization study for ultra-long cycle fast reactor core concept, Ann. Nucl. Energy, 73, 145, 10.1016/j.anucene.2014.06.030
Tak, 2015, Feasibility study on ultralong-cycle operation and material performance for compact liquid metal-cooled fast reactors: a review work, Int. J. Energy Res., 39, 1859, 10.1002/er.3384
Toppel, 1983
Xu, 2017, Development of a new parallel SN code for neutron-photon transport calculation in 3-D cylindrical geometry, Prog. Nucl. Energy, 1, 1, 10.1016/j.pnucene.2016.09.005
Yokoyama, 2006
Zheng, 2018, SARAX: a new code for fast reactor analysis part II: verification, validation and uncertainty quantification, Nucl. Eng. Des., 331, 41, 10.1016/j.nucengdes.2018.02.033
Zheng, 2018, SARAX: a new code for fast reactor analysis part I: methods, Nucl. Eng. Des., 340, 421, 10.1016/j.nucengdes.2018.10.008
Zhou, 2014, LAVENDER: a steady-state core analysis code for design studies of accelerator driven subcritical reactors, Nucl. Eng. Des., 278, 434, 10.1016/j.nucengdes.2014.07.027
Zhou, 2013, The measurement and analysis of CEFR sodium void reactivity effect