Use of International Criticality Safety Benchmark Evaluation Project Data for Validation of the Nuclear Data Library BAS

2003 ◽  
Vol 145 (2) ◽  
pp. 234-246 ◽  
Author(s):  
V. M. Shmakov ◽  
V. D. Lyutov ◽  
V. A. Bekhterev
2020 ◽  
Vol 239 ◽  
pp. 22006
Author(s):  
Donny Hartanto ◽  
Bassam Khuwaileh ◽  
Peng Hong Liem

This paper presents the benchmark evaluation of the new ENDF/B-VIII.0 nuclear library for the OECD/NEA Medium 1000 MWth Sodium-cooled Fast Reactor (SFR). There are 2 SFR cores: metallic fueled (MET-1000) and oxide fueled (MOX-1000). The continuous-energy Monte Carlo Serpent2 code was used as the calculation tool. Various nuclear libraries such as ENDF/B-VII.1 and JENDL-4.0 were included to be compared with the newest ENDF/B-VIII.0. The evaluated parameters are k,βeff, sodium void reactivity (∆ρNa), Doppler constant (∆ρDoppler), and control rod worth (∆ρCR).


2003 ◽  
Vol 145 (2) ◽  
pp. 247-255 ◽  
Author(s):  
T. T. Ivanova ◽  
M. N. Nikolaev ◽  
K. F. Raskach ◽  
E. V. Rozhikhin ◽  
A. M. Tsiboulia

2017 ◽  
Vol 146 ◽  
pp. 02002 ◽  
Author(s):  
Zhigang Ge ◽  
Haicheng Wu ◽  
Guochang Chen ◽  
Ruirui Xu

2011 ◽  
Vol 59 (2(3)) ◽  
pp. 1052-1056 ◽  
Author(s):  
Z. G. Ge ◽  
Z. X. Zhao ◽  
H. H. Xia ◽  
Y. X. Zhuang ◽  
T. J. Liu ◽  
...  

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