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Pyeon, C. H.*; Oizumi, Akito; Katano, Ryota; Fukushima, Masahiro
Nuclear Science and Engineering, 199(3), p.429 - 444, 2025/03
Times Cited Count:0 Percentile:0.00(Nuclear Science & Technology)Experimental analyses of neptunium-237 (Np), americium-241 (
Am), and
Am fission and
Np capture reaction rates are conducted by the Serpent 2 code together with ENDF/B-VIII.0 and JENDL-5, using experimental data at neutron spectra of thermal and intermediate regions obtained in the solid-moderated and solid-reflected cores with highly-enriched uranium fuel at the Kyoto University Critical Assembly. Also, uncertainty quantification of fission and capture reaction rate ratios of test samples of
Np,
Am and
Am with reference samples of uranium-235 (
U) and gold-197 (
Au) are evaluated by the MARBLE code system. In terms of fission reaction rate ratios of
Np/
U,
Am/
U and
Am/
U, a comparison between experiments and Serpent 2 calculations shows an accuracy about 5, 15 and 10%, respectively, together with ENDF/B-VIII.0 and JENDL-5. For capture reaction rate ratios of
Np/
Au, Serpent 2 calculations reveal a fairly good accuracy at the thermal neutron spectrum. The total uncertainties of
Np/
U,
Am/
U and
Am/
U fission reaction rate ratios by MARBLE with the covariance data of ENDF/B-VIII.0 and JENDL-5 are found to be about 4% at most in all cores, except for about 8% of
Am/
U with ENDF/B-VIII.0 at the intermediate neutron spectrum.
Yokoyama, Kenji; Hazama, Taira; Taninaka, Hiroshi; Oki, Shigeo
JAEA-Data/Code 2024-007, 41 Pages, 2024/10
The third version of the versatile reactor analysis code system, MARBLE3, has been developed. In the development of the former version of MARBLE, object-oriented scripting language Python (Python2) had been used and then the latest version of Python (Python3) was released. However, due to its backward incompatibility, MARBLE no longer worked with Python3. For this reason, MARBLE3 has been fully modified and maintained to work with Python3. In MARBLE3, newly developed analysis codes and newly proposed calculation methods were incorporated, and the user interface was extended and solvers were reimplemented for maintainability, extensibility, and flexibility. In MARBLE3, the three-dimensional hexagonal/triangular transport code MINISTRI Ver.7 (MINISTRI7) and the three-dimensional hexagonal/triangular diffusion code D-MINISTRI are available as the new analysis codes. These codes can be used in the neutronics analysis system SCHEME and the fast reactor burnup analysis system OPRHEUS, which are the subsystems of MARBLE. In addition, the user interface of CBG, a core analysis system embedded in MARBLE, was extended so that the diffusion and transport calculation solvers for the 2-dimensional RZ system of CBG can be used on SCHEME. On the other hand, MARBLE3 has extended the functionality of the burnup calculation solver so that it can use the numerical methods proposed in the papers on the improvement of the Chebyshev rational function approximation method and the minimax polynomial approximation method. From the viewpoint of maintainability, the point reactor kinetics solver POINTKINETICS, which was introduced in MARBLE2, has been newly reworked as the KINETICS solver in MARBLE3.
Nabialek, A.*; Chumak, O.*; Seki, Takeshi*; Takanashi, Koki; Baczewski, L. T.*; Szymczak, H.*
IEEE Transactions on Magnetics, 59(11), p.2501405_1 - 2501405_5, 2023/11
Times Cited Count:2 Percentile:28.34(Engineering, Electrical & Electronic)Nabialek, A.*; Chumak, O. M.*; Aleshkevych, P.*; Domagala, J. Z.*; Pacewicz, A.*; Salski, B.*; Krupka, J.*; Seki, Takeshi*; Takanashi, Koki; Baczewski, L. T.*; et al.
Scientific Reports (Internet), 13, p.17016_1 - 170169, 2023/10
Times Cited Count:4 Percentile:47.87(Multidisciplinary Sciences)Shigeta, Iduru*; Oku, Shuta*; Kubota, Takahide*; Kimura, Shojiro*; Seki, Takeshi*; Shinozaki, Bunju*; Awaji, Satoshi*; Takanashi, Koki; Hiroi, Masahiko*
AIP Advances (Internet), 13(2), p.025116_1 - 025116_5, 2023/02
Times Cited Count:1 Percentile:12.23(Nanoscience & Nanotechnology)Kataoka, Takahiro*; Naoe, Shota*; Murakami, Kaito*; Yukimine, Ryohei*; Fujimoto, Yuki*; Kanzaki, Norie; Sakoda, Akihiro; Mitsunobu, Fumihiro*; Yamaoka, Kiyonori*
Journal of Clinical Biochemistry and Nutrition, 70(2), p.154 - 159, 2022/03
Times Cited Count:3 Percentile:20.55(Nutrition & Dietetics)Yokoyama, Kenji; Jin, Tomoyuki; Hirai, Yasushi*; Hazama, Taira
JAEA-Data/Code 2015-009, 120 Pages, 2015/07
The second version of the versatile reactor analysis code system, MARBLE2, has been developed. A lot of new functions have been added inMARBLE2 by using the base technology developed in the first version (MARBLE1). Introducing the remaining functions of the conventional code system (JOINT-FR and SAGEP-FR), MARBLE2 enables one to execute almost all analysis functions of the conventional code system with the unified user interfaces of its subsystem, SCHEME. In particular, the sensitivity analysis functionality is available in MARBLE2. On the other hand, new built-in solvers have been developed, and existing ones have been upgraded. Furthermore, some other analysis codes and libraries developed in JAEA have been consolidated and prepared in SCHEME. In addition, several analysis codes developed in the other institutes have been additionally introduced as plug-in solvers. Consequently, -ray transport calculation and heating evaluation become available. As for another subsystem, ORPHEUS, various functionality updates and speed-up techniques have been applied based on user experience of MARBLE1 to enhance its usability.
Nakagome, Yoshihiro*; Shimizu, Kenichi
Kaku Busshitsu Kanri Senta Nyusu, 34(2), p.14 - 19, 2005/02
RERTR(Reduced Enrichment for Research and Test Reactors) for 2004 was held at IAEA in Vienna of Austria, An author and Professor Nakagome(Kyoto University) attended this internationalmeeting and the author presented "Status of Reduced Enrichment Program for Research Reactors in Japan" with Dr.Nakagome. JNMCC(Japan Nuclear Material Control Center) requested to present a report of 2004 RERTR international Meeting and related content for the author and Dr.Nakagome. the content of the report described the meeting content and related issue which related US FRR SNF(Foregin Reserach Reactors Spent Nuclear Fuels) Acceptance Program.
Yamasaki, Atsushi*; Imada, Shin*; Arai, Ryuji*; Utsunomiya, Hiroshi*; Suga, Shigemasa*; Muro, Takayuki*; Saito, Yuji; Kanomata, Takeshi*; Ishida, Shoji*
Physical Review B, 65(10), p.104410_1 - 104410_6, 2002/03
Times Cited Count:63 Percentile:89.39(Materials Science, Multidisciplinary)The magnetic circular dichroism (MCD) of core-level absorption [x-ray absorption spectroscopy (XAS)] spectra in the soft x-ray region has been measured for the ferromagnetic Heusler alloys CoTiSn, Co
ZrSn, and Co
NbSn. The many-peak structures which are clearly observed in the Co 2p-3d XAS-MCD spectra cannot be well explained by atomic multiplet calculations but are better explained by the Co 3d unoccupied states predicted by linear muffin-tin orbital atomic sphere approximation band structure calculations. The MCD spectra show an obvious contribution of the orbital angular momentum component to the magnetic moment in these alloys. The ratio between the orbital angular momentum and spin derived from the MCD spectra varies by more than a factor of 2 within these alloys. The mechanism of this variation is discussed in comparison with the band structure calculations.
; ; Morii, Yukio; ; Katano, Susumu; Funahashi, Satoru; H.R.Child*
Mater. Trans. JIM, 32(11), p.1011 - 1016, 1991/00
Times Cited Count:4 Percentile:47.48(Materials Science, Multidisciplinary)no abstracts in English
Okamoto, Tsuyoshi*; Nishimura, Hideo
JAERI-M 90-031, 89 Pages, 1990/02
no abstracts in English
Nishimura, Hideo; Okamoto, Tsuyoshi*
31st Annual Meeting Proc. of Nuclear Materials Management,Vol. 19, p.518 - 523, 1990/00
no abstracts in English
Arigane, Kenji
JAERI-M 87-063, 133 Pages, 1987/04
no abstracts in English