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Fujimoto, Nozomu*; Fukuda, Kodai*; Honda, Yuki*; Tochio, Daisuke; Ho, H. Q.; Nagasumi, Satoru; Ishii, Toshiaki; Hamamoto, Shimpei; Nakano, Yumi*; Ishitsuka, Etsuo
JAEA-Technology 2021-008, 23 Pages, 2021/06
The effect of mesh division around the burnable poison rod on the burnup calculation of the HTTR core was investigated using the SRAC code system. As a result, the mesh division inside the burnable poison rod does not have a large effect on the burnup calculation, and the effective multiplication factor is closer to the measured value than the conventional calculation by dividing the graphite region around the burnable poison rod into a mesh. It became clear that the mesh division of the graphite region around the burnable poison rod is important for more appropriately evaluating the burnup behavior of the HTTR core..
Sugino, Kazuteru; Takino, Kazuo
JAEA-Data/Code 2019-011, 110 Pages, 2020/01
A deterministic discrete ordinates method (SN method) transport calculation code for three-dimensional hexagonal geometry has been developed as the MINISTRI code (Ver. 7.0). MINISTRI is based on the triangle-mesh finite difference method, which can perform neutron transport calculations with high accuracy for cores of fast power reactors and assemblies of the Russian BFS critical facility. The present study has derived a proper scheme for remarkably improving the convergence of MINISTRI by investigating the issue of previous MINISTRI (Ver. 1.1), which sometimes plays a poor convergence performance in calculations for large-scale power reactor cores. The verification test of improved MINISTRI has been carried out for various cores by setting the reference result as the multi-group Monte-Carlo calculation with the same cross-sections as used in MINISTRI. As a result, it is found that the agreements are within 0.1% for eigenvalues and within 0.7% for power distributions. Thus, the satisfying accuracy of MINISTRI has been confirmed. In order to reduce the calculation time, the initial diffusion calculation scheme and the parallel processing have been implemented. As a result, the calculation time is reduced to the approximately one tenth compared with previous MINISTRI. Furthermore, adoption of the treatment of the anisotropic cell streaming effect, preparation of the perturbation calculation tool, implementation of the function for specification of the triangle-mesh-wise material and merging of the hexagonal-mesh calculation code MINIHEX have been carried out. Thus, the versatility of MINISTRI has been enhanced.
Research Committee on Reactor Physics
JAERI-Research 2004-004, 409 Pages, 2004/03
This report summarizes the second phase (FY2001-2002) activity of "the Working Party (WP) on Reactor Physics for LWR Next Generation Fuels". The next generation fuels mean the ones aiming at further extended burn-up such as 70GWd/t over the current design. In the WP, the benchmark activity has been conducted to investigate and improve the calculation accuracy of the nuclear characteristics of the next generation fuels. In the second phase activity, all benchmark results were compiled and compared. Based on the comparison, the present status of calculation accuracy for the next generation fuels has been confirmed, and the factors causing the calculation differences were analyzed in detail. Moreover, analyses of the post irradiation and critical experiments with the codes used in the benchmark were reviewed, and future experiments and research subjects necessary to reduce the calculation differences were discussed and proposed.
Unesaki, Hironobu*; Okumura, Keisuke; Kitada, Takanori*; Saji, Etsuro*
Transactions of the American Nuclear Society, 88, p.436 - 438, 2003/06
In order to investigate the calculation accuracy of the nuclear characteristics of LWR next generation fuels, the Research Committee on Reactor Physics organized by JAERI has proposed "Reactor Physics Benchmark for LWR Next Generation Fuels". The next generation fuels aim at very high burn-up of about 70GWd/t in PWR or BWR with UO or MOX fuels whose fissile enrichments may exceed the Japanese regulatory limitations for the current LWR fuels such as 5wt.% U-235. Until now, twelve organizations have pariticipated in the benchmark activity. From the comparison with the cell burn-up calculation results using different codes and library data, status of the calculation accuracy and future subjects are clarified.
Okumura, Keisuke; Unesaki, Hironobu*; Kitada, Takanori*; Saji, Etsuro*
Proceedings of International Conference on the New Frontiers of Nuclear Technology; Reactor Physics, Safety and High-Performance Computing (PHYSOR 2002) (CD-ROM), 10 Pages, 2002/10
In order to investigate the calculation accuracy of the nuclear characteristics of LWR next generation fuels, the Research Committee on Reactor Physics organized by Japan Atomic Energy Research Institute has proposed "Reactor Physics Benchmark for LWR Next Generation Fuels". The next generation fuels aim at very high burn-up of about 70GWd/t in PWR or BWR with UO2 or MOX fuels whose fissile enrichments may exceed the Japanese regulatory limitations for the current LWR fuels such as 5wt.% U-235. Twelve organizations have carried out the analyses of the benchmark problems with different codes and data, and their submitted results have been compared. As a result, status of accuracy with the current data and method and some problems to be solved in the future were clarified.
Research Committee on Reactor Physics
JAERI-Research 2001-046, 326 Pages, 2001/10
The Working Party on Reactor Physics for LWR Next Generation Fuels in the Research Committee on Reactor Physics, which is organized by the Japan Atomic Energy Research Institute, has recently proposed a series of benchmark problems to investigate the calculation accuracy of the nuclear characteristics of LWR next generation fuels. The next generation fuels mean the ones aiming for further extended burnup such as 70GWd/t over the current design. The resultant specifications of the benchmark problem therefore neglect some of the current limitations such as 5wt%235U to achieve the above-mentioned target. The Working Party proposed six benchmark problems, which consist of pin-cell, PWR assembly and BWR assembly geometries loaded with uranium and MOX fuels, respectively. The present report describes the detailed specifications of the benchmark problems. The results of preliminary analyses performed by the eleven member organizations and their comparisons are also presented.
Fujimoto, Nozomu; Yamashita, Kiyonobu
JAERI-Research 99-059, p.43 - 0, 1999/11
no abstracts in English
Fujimoto, Nozomu; Yamashita, Kiyonobu; Akino, Fujiyoshi
JAERI-Research 99-052, p.51 - 0, 1999/09
no abstracts in English
; Suyama, Kenya;
Journal of Nuclear Science and Technology, 35(3), p.240 - 242, 1998/03
Times Cited Count:1 Percentile:15.05(Nuclear Science & Technology)no abstracts in English
Okumura, Keisuke; ;
JAERI-Data/Code 96-015, 445 Pages, 1996/03
no abstracts in English
Okuno, Hiroshi; Naito, Yoshitaka; Sakurai, Y.*
Journal of Nuclear Science and Technology, 28(10), p.958 - 960, 1991/10
no abstracts in English
Sakurai, Y.*; Okuno, Hiroshi; Naito, Yoshitaka
JAERI-M 91-137, 35 Pages, 1991/09
no abstracts in English
Okuno, Hiroshi;
JAERI-M 91-107, 49 Pages, 1991/08
no abstracts in English
JAERI-M 91-108, 25 Pages, 1991/07
no abstracts in English
C-J.Jeong*; Okumura, Keisuke; ; Tanaka, Kenichi*
Journal of Nuclear Science and Technology, 27(6), p.515 - 523, 1990/06
no abstracts in English
Naito, Yoshitaka; ; Masukawa, Fumihiro;
JAERI-M 90-019, 62 Pages, 1990/02
no abstracts in English
Tsuchihashi, Keichiro; Akino, Fujiyoshi
Journal of Nuclear Science and Technology, 24(12), p.1055 - 1065, 1987/12
Times Cited Count:2 Percentile:29.53(Nuclear Science & Technology)no abstracts in English
;
Journal of Nuclear Science and Technology, 22(10), p.853 - 856, 1985/00
Times Cited Count:2 Percentile:39.87(Nuclear Science & Technology)no abstracts in English
; ; ; ; ;
JAERI 1285, 242 Pages, 1983/01
no abstracts in English