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Okamoto, Naritoshi; Komeno, Akira; Seya, Atsumasa; Inaba, Hideki*; Terakado, Shinichi*; Higuchi, Masashi*
JAEA-Data/Code 2025-022, 497 Pages, 2026/03
The Plutonium Fuel Third Development Laboratory of the Nuclear Fuel Cycle Engineering Laboratories has applied for a change of use permit (hereinafter referred to as "license") for plutonium fuel facilities. For the criticality safety design of gloveboxes and equipment/instruments handling mixed oxide (MOX), various criticality calculation codes are used. The most recent employs the 3D Monte Carlo calculation code KENO-V.a embedded in the SCALE 4.4 code system, along with the 27-group ENDF/B-IV neutron cross-section library. SCALE 4.4 was released by the Oak Ridge National Laboratory (ORNL) in the US in 1998, and has now been in use for 27 years. ORNL has continuously improved its functionality, with SCALE 6.3.2 released in 2024. When designing and constructing new MOX fuel facilities, it is desirable to obtain a license using criticality calculation codes based on the latest knowledge. However, it is necessary to verify that these codes have sufficient reliability. Therefore, in 2018, benchmark calculations were performed using the 252-group ENDF/B-VII.1 neutron cross-section library (v7-252n) for two versions of the criticality calculation sequences KENO-V.a and KENO-VI from SCALE 6.2.3, based on past criticality experimental setups. The estimated critical-limiting multiplication factor was calculated. The results indicate that these codes can be used with sufficient confidence for criticality safety design of MOX fuel facilities.
Yoshida, Takeru; Maeda, Koji; Sekio, Yoshihiro; Tomita, Hideki*; Iwata, Yoshihiro; Hirai, Mutsumi*; Mizokami, Masato*; Sakamoto, Tetsuo*
Scientific Reports (Internet), 16, p.9865_1 - 9865_8, 2026/03
Times Cited Count:0 Percentile:0.00(Multidisciplinary Sciences)Kato, Taichi*; Shiihara, Yoshinori*; Mori, Hideki*; Tsuru, Tomohito; Matsunaka, Daisuke*
Zairyo, 75(2), p.109 - 115, 2026/02
Machine-learning-based molecular dynamics (ML-MD) has emerged as a promising approach to resolving the trade-off between accuracy and computational cost in atomic simulations. The most conventional method in ML-MD, total energy learning (TEL), trains models by matching the sum of predicted atomic energies to the total energy of the system. However, because calculating total energy requires information from all atoms in the system, TEL poses limitations for flexible data refinement. To address this issue, we have developed atomic energy learning (AEL), which enables atomic level data selection by directly using each atom's energy as training data. As a fundamental study, we compare AEL and TEL using datasets based on the Embedded Atom Method (EAM). The results demonstrate the effectiveness of selective data sampling in controlling model accuracy and reveal the advantage of AEL in evaluating atomic energies near defects through targeted data selection.
Be nuclear magnetic resonance in UBe
; Itinerant-localized duality and possible Fermi surface reconstruction at high magnetic fieldMatsuki, Rintaro*; Minami, Shoko*; Kotegawa, Hisashi*; Harima, Hisatomo*; Haga, Yoshinori; Yamamoto, Etsuji; Onuki, Yoshichika*; To, Hideki*
Journal of the Physical Society of Japan, 94(12), p.124702_1 - 124702_8, 2025/11
Times Cited Count:0 Percentile:0.00(Physics, Multidisciplinary)
2022)Aso, Tomokazu; Ariyoshi, Gen; Muto, Hideki*; Tanaka, Shigeto*
JAEA-Technology 2025-005, 51 Pages, 2025/10
The cryogenic hydrogen system of the J-PARC center is one of the most important pieces equipment, which is a refrigeration system for moderating (cooling) the high energy neutrons generated the spallation neutron source of the Material and Life Science Experimental Facility (MLF) that is used by many users from Japan and abroad. Since the first operation of the MLF for neutron use in 2008, the cryogenic hydrogen system has been continuously operated and maintained, and related technology development has been carried out. This report summarized these activities over the past five years.
Ishikawa, Akihisa; Segawa, Mariko; Toh, Yosuke; Watanabe, Kenichi*; Masuda, Akihiko*; Matsumoto, Tetsuro*; Yamazaki, Atsushi*; Yoshihashi, Sachiko*; Uritani, Akira*; Harano, Hideki*
Journal of Radiation Research (Internet), 66(5), p.563 - 569, 2025/09
Times Cited Count:1 Percentile:49.60(Biology)Tamura, Yukiko*; Arakawa, Masato*; Takenaka, Mikihito*; Nakanishi, Yohei*; Fujinami, So*; Shibata, Motoki*; Yamamoto, Katsuhiro*; Miyata, Noboru*; Yamada, Masako*; Seto, Hideki*; et al.
Polymer, 333, p.128662_1 - 128662_8, 2025/08
Times Cited Count:1 Percentile:31.99(Polymer Science)
catalyst condition at J-PARC cryogenic moderator systemAriyoshi, Gen; Tatsumoto, Hideki*; Teshigawara, Makoto; Hasegawa, Takumi*; Shiro, Yuki*; Horikawa, Yuka*
IOP Conference Series; Materials Science and Engineering, 1327(1), p.012155_1 - 012155_6, 2025/05
Times Cited Count:0 Percentile:0.00(Thermodynamics)The Spallation Neutron Source (SNS) at the Oak Ridge National Laboratory in the United States of America, which operates at 1.4 MW of high-power proton beam, has recently measured "back conversion production" in which parahydrogen, a nuclear spin isomer, is converted to orthohydrogen in an intense neutron field in a liquid hydrogen circulation system not installing any catalyst, for the first time in the world. The amount of para-to-orthohydrogen back conversion was 0.374 [m
/MW/day]. Comparing parahydrogen and orthohydrogen, the total neutron cross section differs more than two orders of magnitude, so the increase in orthohydrogen has a significant impact on the generated neutron performance. Therefore, in the J-PARC hydrogen circulation system, a catalyst is introduced to maintain the parahydrogen state. However, at present, methods have not been developed yet to directly diagnose catalyst performance and/or degradation in-situ. In this study, we devised a new method to easily and intentionally change the amount of orthohydrogen in the J-PARC hydrogen circulation system, and attempted to evaluate catalyst kinetics by intentionally introducing an increase in orthohydrogen equivalent to back conversion into the circulation system. This method has the potential to contribute to the in-situ diagnostic catalyst characterization and to the calculation of neutron performance that depends on the ortho-to-parahydrogen ratio.
Abe, Noriaki; Hoshi, Hiroyuki*; Haji, Toshiki*; Sato, Katsushi*; Niki, Sota*; Hirata, Takafumi*; Iwano, Hideki*; Danhara, Toru*
Chishitsugaku Zasshi (Internet), 131(1), p.59 - 70, 2025/04
To constrain the upper limit of the depositional age of the Tanabe Group, Early-Middle Miocene forearc basin deposit, this study obtained the detrital zircon U-Pb ages separated from eight sedimentary rock samples. We obtained 221 concordant ages from 330 zircon grains. The youngest grain age was 19.4 Ma, suggesting the upper limit of the depositional age is younger than 19.4 Ma, and no grain showed the depositional age indicated by foraminifera (16.3-15.1 Ma). Large-scale volcanic activities occurred in the Middle Miocene around Kii Peninsula, mainly after 15 Ma. The lack of grain younger than 15 Ma suggests that the Tanabe Group was deposited before 15 Ma. Sluggish volcanic activities in the provenance areas before 15 Ma may have caused the lack of zircons having ages close to the depositional period inferred from foraminifera.

Yamauchi, Hiroki; Metoki, Naoto; Watanuki, Ryuta*; Hong, T.*; Fernandez-Baca, J. A.*; Hagihara, Masato; Masuda, Takatsugu*; Yoshizawa, Hideki*; Ito, Shinichi*
Journal of the Physical Society of Japan, 94(5), p.054705_1 - 054705_8, 2025/04
Times Cited Count:2 Percentile:66.10(Physics, Multidisciplinary)Taniguchi, Takumi; Matsumoto, Saori; Hiraki, Yoshihisa; Sato, Junya; Fujita, Hideki*; Kaneda, Yoshihisa*; Kuroki, Ryoichiro; Osugi, Takeshi
JAEA-Review 2024-059, 20 Pages, 2025/03
The basic performance required for solidifying waste into cement, such as fluidity before curing and strength after curing, is expected to be affected by the chemical effects of substances and components contained in the waste. The fluidity before curing and the strength properties after curing are greatly influenced by the curing speed of the cement. We investigated existing knowledge with a focus on chemical substances that affect the curing speed of cement. In this report, chemical substances that affect fluidity are broadly classified into inorganic substances such as (1) anion species, (2) metal elements such as heavy metals, (3) inorganic compounds as cement admixtures, and (4) organic compounds as cement admixtures. Based on the investigation, we actually added chemicals and measured the setting time. As a result, it was found that there are multiple mechanisms contributing to accelerated hardening. We investigated chemical substances that inhibit the curing reaction of cement, and were able to compile information to consider ingredients that are contraindicated in cement curing.
Kokubun, Yuji; Hosomi, Kenji; Seya, Natsumi; Nagaoka, Mika; Inoue, Kazumi; Koike, Yuko; Hasegawa, Ryo; Kubota, Tomohiro; Hirao, Moe; Iizawa, Shogo; et al.
JAEA-Review 2024-053, 116 Pages, 2025/03
Based on the regulations (the safety regulation of Tokai Reprocessing Plant, the safety regulation of nuclear fuel material usage facilities, the radiation safety rule, the regulation about prevention from radiation hazards due to radioisotopes, which are related with the nuclear regulatory acts, the local agreement concerning with safety and environment conservation around nuclear facilities, the water pollution prevention act, and by law of Ibaraki Prefecture), the effluent control of liquid waste discharged from the Nuclear Fuel Cycle Engineering Laboratories of Japan Atomic Energy Agency has been performed. This report describes the effluent control results of the liquid waste in the fiscal year 2023. In this period, the concentrations and the quantities of the radioactivity in liquid waste discharged from the reprocessing plant, the plutonium fuel fabrication facilities, and the other nuclear fuel material usage facilities were much lower than the limits authorized by the above regulations.
Kawasaki, Takuro; Fukuda, Tatsuo; Yamanaka, Satoru*; Murayama, Ichiro*; Kato, Takanori*; Baba, Masaaki*; Hashimoto, Hideki*; Harjo, S.; Aizawa, Kazuya; Tanaka, Hirohisa*; et al.
Journal of Applied Physics, 137(9), p.094101_1 - 094101_7, 2025/03
Times Cited Count:1 Percentile:36.38(Physics, Applied)Kojima, Yuya*; Murakawa, Hideki*; Sugimoto, Katsumi*; Kondo, Teppei*; Abe, Yuta; Aizawa, Kosuke
Proceedings of 13th International Symposium on Measurement Techniques for Multiphase Flows (ISMTMF 2025), 5 Pages, 2025/02
Teshigawara, Makoto; Lee, Y.*; Tatsumoto, Hideki*; Hartl, M.*; Aso, Tomokazu; Iverson, E. B.*; Ariyoshi, Gen; Ikeda, Yujiro*; Hasegawa, Takumi*
Nuclear Instruments and Methods in Physics Research B, 557, p.165534_1 - 165534_10, 2024/12
Times Cited Count:1 Percentile:24.85(Instruments & Instrumentation)At Japanese Spallation Neutron Source in J-PARC, the para-hydrogen fraction was measured by using Raman spectroscopy in-situ for an integrated beam power of 9.4 MW
h at 1 MW operation, to evaluate the functionality of the ferric oxyhydroxide catalyst. This result showed that full functionality of the catalyst was retained up to the 1 MW operation. We attempted to study the effect of neutron scattering driven para to ortho-hydrogen back-conversion rate in the absence of the catalyst effect with a bypass line without catalyst. The measured increase of ortho-hydrogen fraction was 0.44% for an integrated beam power of 2.4 MW
h at 500 kW operation, however, which was considered to be due to not only to neutron collisions in cold moderators but also to the high ortho-hydrogen fraction of initially static liquid hydrogen in the bypass line and passive exudation of quasi-static hydrogen in the catalyst vessel to the main loop.
Kotegawa, Hisashi*; Nakamura, Akira*; Huyen, V. T. N.*; Arai, Yuki*; To, Hideki*; Sugawara, Hitoshi*; Hayashi, Junichi*; Takeda, Keiki*; Tabata, Chihiro; Kaneko, Koji; et al.
Physical Review B, 110(21), p.214417_1 - 214417_8, 2024/12
Times Cited Count:4 Percentile:35.67(Materials Science, Multidisciplinary)Yamamoto, Katsuhiro*; Imai, Tatsuya*; Kawai, Atsuki*; Ito, Eri*; Miyazaki, Tsukasa*; Miyata, Noboru*; Yamada, Norifumi*; Seto, Hideki*; Aoki, Hiroyuki
ACS Applied Materials & Interfaces, 16(48), p.66782 - 66791, 2024/11
Times Cited Count:2 Percentile:18.03(Nanoscience & Nanotechnology)Miyazaki, Tsukasa*; Miyata, Noboru*; Arima-Osonoi, Hiroshi*; Shimokita, Keisuke*; Yamamoto, Katsuhiro*; Takenaka, Mikihito*; Nakanishi, Yohei*; Shibata, Motoki*; Aoki, Hiroyuki; Yamada, Norifumi*; et al.
Colloids and Surfaces A; Physicochemical and Engineering Aspects, 701, p.134928_1 - 134928_8, 2024/11
Times Cited Count:1 Percentile:5.67(Chemistry, Physical)
-ray fieldsKaburagi, Masaaki; Kamada, Kei*; Ishii, Junya*; Matsumoto, Tetsuro*; Manabe, Seiya*; Masuda, Akihiko*; Harano, Hideki*; Kato, Masahiro*; Shimazoe, Kenji*
Journal of Instrumentation (Internet), 19(11), p.P11019_1 - P11019_16, 2024/11
Times Cited Count:2 Percentile:26.42(Instruments & Instrumentation)Miyabe, Masabumi; Iwata, Yoshihiro; Tomita, Hideki*; Morita, Masato*; Sakamoto, Tetsuo*
Spectrochimica Acta, Part B, 221, p.107036_1 - 107036_12, 2024/11
Times Cited Count:6 Percentile:74.48(Spectroscopy)Two-color two-step resonance ionization spectroscopy of neodymium (Nd) was performed to identify more than 120 even-parity autoionizing levels and their candidate J-values. The analysis of the observed autoionizing Rydberg series yielded a value of 44560.11 (43)
(2)
cm
as a more accurate ionization potential of Nd. The saturation method was used to measure the transition cross-sections for some intense ionization transitions. From the measured cross-sections, the ionization efficiencies of some two-step ionization schemes were evaluated using the scheme cross-section formula to obtain several promising schemes.