Nuclear data processing code FRENDY: A verification with HTTR criticality benchmark experiments
暂无分享,去创建一个
Nozomu Fujimoto | Shimpei Hamamoto | Kenichi Tada | Satoru Nagasumi | Etsuo Ishitsuka | Hai Quan Ho | S. Hamamoto | E. Ishitsuka | H. Ho | N. Fujimoto | S. Nagasumi | Kenichi Tada
[1] Kenichi Tada,et al. Development of a Nuclear Data Processing Code FRENDY Version 1 , 2019, 2019 IEEE Nuclear Science Symposium and Medical Imaging Conference (NSS/MIC).
[2] S. Saito,et al. Design of high temperature Engineering Test Reactor (HTTR) , 1994 .
[3] Y. Honda,et al. Numerical investigation of the random arrangement effect of coated fuel particles on the criticality of HTTR fuel compact using MCNP6 , 2017 .
[4] J. Bess,et al. Benchmark Evaluation of Start-Up and Zero-Power Measurements at the High-Temperature Engineering Test Reactor , 2014 .
[5] Yasunobu Nagaya,et al. Development and verification of a new nuclear data processing system FRENDY , 2017 .
[6] K. Shibata,et al. JENDL-4.0: A New Library for Nuclear Science and Engineering , 2011 .
[7] Satoshi Shimakawa,et al. Characteristic test of initial HTTR core , 2004 .
[8] R.E. MacFarlane,et al. The NJOY Nu-clear Data Processing System Version 91 , 1994 .
[9] N. M. Larson,et al. ENDF/B-VII.1 Nuclear Data for Science and Technology: Cross Sections, Covariances, Fission Product Yields and Decay Data , 2011 .