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Journal Articles

Activation experiment of the $$^{rm nat}$$Ag(p,X) reaction at J-PARC

Sugihara, Kenta*; Meigo, Shinichiro; Iwamoto, Hiroki; Maekawa, Fujio

JPS Conference Proceedings (Internet), 45, p.011181_1 - 011181_10, 2026/06

It is essential to estimate the residual gamma-ray dose rate at accelerator facilities, such as accelerator-driven system. Even though improvements of computer performance enabled us to predict nuclide production cross sections by physics models, the prediction accuracy of the models should be confirmed more. Thus, we have been measuring the nuclide production cross sections by the proton bombardment on various targets with activation technique at J-PARC. In this study, we measured nuclide production cross section of the $$^{rm nat}$$Ag(p,X) reaction.

Journal Articles

A Machine leaning-based approach to estimate nuclide production cross sections

Iwamoto, Hiroki; Meigo, Shinichiro; Sugihara, Kenta*

JPS Conference Proceedings (Internet), 45, p.011179_1 - 011179_7, 2026/06

The nuclide production cross sections are crucial for evaluating the radioactivity of activation products in accelerators and nuclear facilities. Although the production of radionuclides in spallation reactions can be explained using physics models like the nuclear cascade plus evaporation model, accurately and comprehensively reproducing experimental values remains challenging. To address this problem, we have developed a machine learning (ML) model to comprehensively estimate nuclide production cross sections for target materials. The model is trained on experimental data from the nuclear reaction database EXFOR and can estimate nuclide production cross sections even in data-poor regions by utilizing transfer learning. In a previous study, we demonstrated that our model can comprehensively estimate $$^7$$Be ($$T_{1/2} = 53.22$$ d) and $$^3$$H ($$T_{1/2} = 12.32$$ y) production cross sections for a wide range of targets. In this study, we apply the ML model to nuclides important for accelerator facility design and astrophysics, such as $$^3$$He, $$^{10}$$Be ($$T_{1/2} = 1.387 times 10^6$$ y), $$^{22}$$Na ($$T_{1/2} = 2.6$$ y), and $$^{24}$$Na ($$T_{1/2} = 14.956$$ h), showing that it can comprehensively estimate their production cross sections.

Journal Articles

A Semi-implicit weakly compressible solver for gas-liquid two-phase flows

Sugihara, Kenta; Onodera, Naoyuki*; Idomura, Yasuhiro; Sitompul, Y.; Yamashita, Susumu

Journal of Computational Physics, 547, p.114534_1 - 114534_25, 2026/02

 Times Cited Count:0 Percentile:0.00(Computer Science, Interdisciplinary Applications)

Journal Articles

Photoneutron emission process on nuclei around A = 200 for giant dipole resonance energies based on neutron energy and angular distribution

Nguyen, T. H. T.; Sanami, Toshiya*; Yamazaki, Hirohito*; Iwamoto, Nobuyuki; Itoga, Toshiro*; Kirihara, Yoichi; Lee, E.*; Sugihara, Kenta*; Miyamoto, Shuji*; Hashimoto, Satoshi*; et al.

Physics Letters B, 870, p.139900_1 - 139900_8, 2025/11

 Times Cited Count:0 Percentile:0.00(Astronomy & Astrophysics)

JAEA Reports

Conceptual study of J-PARC Proton Beam Irradiation Facility

Meigo, Shinichiro; Iwamoto, Hiroki; Sugihara, Kenta*; Hirano, Yukinori*; Tsutsumi, Kazuyoshi*; Saito, Shigeru; Maekawa, Fujio

JAEA-Technology 2024-026, 123 Pages, 2025/03

JAEA-Technology-2024-026.pdf:14.22MB

Based on the design of the ADS Target Test Facility (TEF-T) at the J-PARC Transmutation Experimental Facility, a conceptual study was conducted on the J-PARC proton beam irradiation facility. This research was carried out based on the recommendations of the Nuclear Transmutation Technology Evaluation Task Force of the MEXT. The recommendations state that it is desirable to consider facility specifications that can make the most of the benefits of using the existing J-PARC proton accelerator while also solving the engineering issues of the ADS. We considered facilities that could respond to a variety of needs while reducing the facilities that were not needed in the TEF-T design. In order to clarify these diverse needs, we investigated the usage status of representative accelerator facilities around the world. As a result, it became clear that the main purposes of these facilities were (1) Material irradiation, (2) Soft error testing of semiconductor devices using spallation neutrons, (3) Production of RI for medical use, and (4) Proton beam use, and we investigated the facilities necessary for these purposes. In considering the facility concept, we assumed a user community in 2022 and reflected user opinions in the facility design. This report summarizes the results of the conceptual study of the proton irradiation facility, various needs and responses to them, the roadmap for facility construction, and future issues.

Journal Articles

Overview of PHITS Ver.3.34 with particular focus on track-structure calculation

Ogawa, Tatsuhiko; Hirata, Yuho; Matsuya, Yusuke; Kai, Takeshi; Sato, Tatsuhiko; Iwamoto, Yosuke; Hashimoto, Shintaro; Furuta, Takuya; Abe, Shinichiro; Matsuda, Norihiro; et al.

EPJ Nuclear Sciences & Technologies (Internet), 10, p.13_1 - 13_8, 2024/11

The latest updates on PHITS, a versatile radiation transport code, focusing specifically on track-structure models are presented. Track structure calculations are methods used to simulate the movement of charged particles while explicitly considering each atomic reaction. Initially developed for radiation biology, these calculation methods aimed to analyze the radiation-induced damage to DNA and chromosomes. Several track-structure calculation models, including PHITS-ETS, PHITS-ETS for Si, PHITS-KURBUC, ETSART, and ITSART, have been developed and implemented to PHITS. These models allow users to study the behavior of various particles at the nano-scale across a wide range of materials. Furthermore, potential applications of track-structure calculations have also been proposed so far. This collection of track-structure calculation models, which encompasses diverse conditions, opens up new avenues for research in the field of radiation effects.

Journal Articles

Measurement of the spallation neutron spectrum by unfolding at 180$$^{circ}$$ from 3-GeV protons and $$^{nat}$$Hg with the $$^{209}$$Bi(n,xn) reactions

Sugihara, Kenta*; Meigo, Shinichiro; Iwamoto, Hiroki; Maekawa, Fujio

JAEA-Conf 2024-002, p.162 - 167, 2024/11

A neutron energy spectrum is important for shielding design at an Accelerator-Driven System facility (1.5-GeV p + Lead Bismuth Eutectic). A similar spectrum can be obtained at J-PARC (3-GeV proton + $$^{nat}$$Hg). To check the validity of the unfolding, the unfolding with the $$^{209}$$Bi(n,xn) reactions and the response functions (JENDL/HE-2007 and TALYS) was applied. In our poster, we present the derivation of the spectrum and comparison with the spectrum with a Time-of-Flight technique.

Journal Articles

Bubble flow analysis using multi-phase field method

Sugihara, Kenta; Onodera, Naoyuki; Sitompul, Y.; Idomura, Yasuhiro; Yamashita, Susumu

EPJ Web of Conferences, 302, p.03002_1 - 03002_10, 2024/10

 Times Cited Count:3 Percentile:98.30(Computer Science, Interdisciplinary Applications)

In simulations of gas-liquid two-phase flows using conventional interface capture methods, we observed that when bubbles come close to each other, they tend to merge numerically, despite experimental evidence indicating that they would repel each other. Given the significant impact of sequential numerical coalescence on flow patterns, it is necessary to regulate the merging behavior of close bubbles. To address this issue, we introduced the Multi- Phase Field (MPF) method, which mitigates bubble coalescence by applying an independent fluid fraction function to each bubble. In this study, we employed the MPF based on the N-phase model to minimize numerical errors associated with surface interactions at triple junction points. Additionally, we implemented the Ordered Active Parameter Tracking (OAPT) method to efficiently store several hundreds of fluid fraction functions. To validate the MPF method, we conducted analysis of turbulent bubbly pipe flows and compared the results against experimental data from Colin et al. The validation results showed reasonable agreements with respect to the bubble distribution and the flow velocity profiles.

Journal Articles

Gas entrainment simulation for fast reactors using freesurface lattice Boltzmann method

Sitompul, Y.; Sugihara, Kenta; Onodera, Naoyuki; Idomura, Yasuhiro

EPJ Web of Conferences, 302, p.05004_1 - 05004_10, 2024/10

 Times Cited Count:1 Percentile:85.40(Computer Science, Interdisciplinary Applications)

In fast reactor designs, it is of critical importance to avoid gas entrainment phenomena due to free-surface vortices. Numerical analysis is one of the key methods to understand these phenomena. However, the challenges in computational efficiency and accuracy of the previous numerical methods lead to exploring the Lattice Boltzmann method (LBM) as an alternative, known for its computational efficiency and capability in simulating complex flows. In this study, we implement free-surface LBM to accelerate gas entrainment analysis, significantly reducing computational costs while maintaining accuracy compared to traditional methods. Simulation results using LBM align well with experimental data, offering a promising avenue for faster analysis in future fast reactor designs.

Journal Articles

Compressible Navier-Stokes formulation for accelerating Poisson solver of gas-liquid two-phase fluid simulations

Onodera, Naoyuki; Sugihara, Kenta; Ina, Takuya; Idomura, Yasuhiro

Keisan Kogaku Koenkai Rombunshu (CD-ROM), 29, 3 Pages, 2024/06

Gas-liquid two-phase flow analysis is one of the most important research topics in nuclear engineering because it is essential for safety evaluation and reactor design. However, it requires large-scale multi-scale simulations, and advanced numerical approaches are needed. To meet this challenge, we have continued to develop the Poisson solver for the multiphase flow analysis code JUPITER. In this study, we aim to improve the convergence of the pressure Poisson solver by formulating the Navier-Stokes equation without using the incompressible approximation. The convergence performance was measured on 8 GPUs for bubbly flow analysis in a circular tube. The results show that the computation time and the number of iterations are reduced by half compared to those using the incompressible approximation, which indicates the usefulness of the formulation in the present study.

Journal Articles

Optimization of phase field variables in bubble rise analysis

Sugihara, Kenta; Onodera, Naoyuki; Sitompul, Y.; Idomura, Yasuhiro; Yamashita, Susumu

Keisan Kogaku Koenkai Rombunshu (CD-ROM), 29, 6 Pages, 2024/06

When calculating a flow containing many bubbles, it is difficult to reproduce the flow pattern observed in experiments because bubbles that are close to each other merge numerically in gas-liquid two-phase flow analysis using the conventional interface capturing method. In this study, the Multi-Phase Field method is used to prevent the numerical bubble merging by representing each bubble using an independent fluid fraction function. The applicability of the proposed method is verified by comparing bubbly flow analysis with experimental results.

Journal Articles

Comprehensive estimation of nuclide production cross sections using a phenomenological approach

Iwamoto, Hiroki; Meigo, Shinichiro; Sugihara, Kenta*

Physical Review C, 109(5), p.054610_1 - 054610_12, 2024/05

 Times Cited Count:3 Percentile:55.75(Physics, Nuclear)

Nuclide production cross sections are crucial in nuclear research, development, space exploration, and astrophysical investigations. Despite their importance, limited experimental data availability restricts the practicality of phenomenological approaches to comprehensive cross-section estimation. To address this, we propose a Gaussian process-based machine learning (ML) model capable of transferring knowledge from elements with abundant data to those with limited or no experimental data. Our ML model not only enables comprehensive cross-section estimations for various elements but also demonstrates predictive capabilities akin to physics models, even in regions with scarce training data.

Journal Articles

Measurement of nuclide production cross sections for GeV-region proton-induced reactions on $$^{rm nat}$$Mg, $$^{rm nat}$$Si, $$^{rm nat}$$Fe, $$^{rm nat}$$Cu, and $$^{rm nat}$$Zn

Sugihara, Kenta*; Meigo, Shinichiro; Iwamoto, Hiroki; Maekawa, Fujio

Nuclear Instruments and Methods in Physics Research B, 549, p.165299_1 - 165299_12, 2024/04

 Times Cited Count:1 Percentile:23.44(Instruments & Instrumentation)

Journal Articles

Recent improvements of the Particle and Heavy Ion Transport code System; PHITS version 3.33

Sato, Tatsuhiko; Iwamoto, Yosuke; Hashimoto, Shintaro; Ogawa, Tatsuhiko; Furuta, Takuya; Abe, Shinichiro; Kai, Takeshi; Matsuya, Yusuke; Matsuda, Norihiro; Hirata, Yuho; et al.

Journal of Nuclear Science and Technology, 61(1), p.127 - 135, 2024/01

 Times Cited Count:348 Percentile:99.98(Nuclear Science & Technology)

The Particle and Heavy Ion Transport code System (PHITS) is a general-purpose Monte Carlo radiation transport code that can simulate the behavior of most particle species with energies up to 1 TeV (per nucleon for ions). Its new version, PHITS3.31, was recently developed and released to the public. In the new version, the compatibility with high-energy nuclear data libraries and the algorithm of the track-structure modes have been improved. In this paper, we summarize the upgraded features of PHITS3.31 with respect to the physics models, utility functions, and application software introduced since the release of PHITS3.02 in 2017.

Journal Articles

Measurement of nuclide production cross sections for proton-induced reactions on $$^{nat}$$Ti and $$^{93}$$Nb at 0.8 and 3.0 GeV

Sugihara, Kenta*; Meigo, Shinichiro; Iwamoto, Hiroki; Maekawa, Fujio

Nuclear Instruments and Methods in Physics Research B, 545, p.165153_1 - 165153_9, 2023/12

 Times Cited Count:2 Percentile:29.70(Instruments & Instrumentation)

Journal Articles

Neutron-production double-differential cross sections of $$^{rm nat}$$Pb and $$^{209}$$Bi in proton-induced reactions near 100 MeV

Iwamoto, Hiroki; Meigo, Shinichiro; Satoh, Daiki; Iwamoto, Yosuke; Ishi, Yoshihiro*; Uesugi, Tomonori*; Yashima, Hiroshi*; Nishio, Katsuhisa; Sugihara, Kenta*; $c{C}$elik, Y.*; et al.

Nuclear Instruments and Methods in Physics Research B, 544, p.165107_1 - 165107_15, 2023/11

 Times Cited Count:4 Percentile:51.43(Instruments & Instrumentation)

The lack of double-differential cross-section (DDX) data for neutron production below the incident proton energy of 200 MeV hinders the validation of spallation models in technical applications, such as research and development of accelerator-driven systems (ADSs). The present study aims to obtain experimental DDX data for ADS spallation target materials in this energy region and identify issues related to the spallation models by comparing them with the analytical predictions. The DDXs for the ($$p, xn$$) reactions of $$^{rm nat}$$Pb and $$^{209}$$Bi in the 100-MeV region were measured over an angular range of 30$$^{circ}$$ to 150$$^{circ}$$ using the time-of-flight method. The measurements were conducted at Kyoto University utilizing the FFAG accelerator. The DDXs obtained were compared with calculation results from Monte Carlo-based spallation models and the evaluated nuclear data library, JENDL-5. Comparison between the measured DDX and analytical values based on the spallation models and evaluated nuclear data library indicated that, in general, the CEM03.03 model demonstrated the closest match to the experimental values. Additionally, the comparison highlighted several issues that need to be addressed in order to improve the reproducibility of the proton-induced neutron-production DDX in the 100 MeV region by these spallation models and evaluated nuclear data library.

JAEA Reports

Optimized phase-field modeling using a modified conservative Allen-Cahn equation for two-phase flows

Sugihara, Kenta; Onodera, Naoyuki; Idomura, Yasuhiro; Yamashita, Susumu

JAEA-Research 2023-006, 47 Pages, 2023/10

JAEA-Research-2023-006.pdf:3.28MB

This report presents a new surface capturing method based on the phase field model for gas-liquid two-phase flows simulation. In the conventional phase field model, the interface correction strength parameter was determined from the maximum flow velocity in the computational domain, but because the interface correction was applied uniformly to the entire space, it was also applied to locations that did not require correction. In the new method, the phase field parameter or the intensity of the phase field model is extended to have a spatial distribution, allowing us to set the optimal parameters depending on the local flow velocity fields. We also propose a method to derive the optimal phase field parameter based on systematic parameter scans using error analysis of the interface advection test and bubble rising calculations. Through benchmark tests of gas-liquid two-phase flows, the proposed model is verified, and it is shown that the proposed model has higher accuracy than the conventional phase field model.

Journal Articles

Optimization of phase field variables in bubble rise analysis

Sugihara, Kenta; Onodera, Naoyuki; Idomura, Yasuhiro; Yamashita, Susumu

Keisan Kogaku Koenkai Rombunshu (CD-ROM), 28, 5 Pages, 2023/06

The Modified conservative Allen-Cahn (MCAC) equation, which assumes a spatial distribution for the interface modification strength $$gamma$$ by the phase field method and weights it using the local velocity distribution and velocity gradient, is proposed. MCAC was applied to bubble rise calculations for four representative shapes, and the results were found to be reasonable in comparison with those of Grace and Annaland et al. In addition, the results obtained by MCAC are equivalent or superior to those of Conservative Allen-Cahn (CAC), and thus MCAC can be considered superior in that it can use appropriate $$gamma$$ even when large velocity differences occur in a part of the computational domain. Finally, this method was applied to the analysis of a bundle system, and it was confirmed that the gas-liquid interface can be captured even for flows in complex channels.

Journal Articles

Measurement of double-differential neutron yields for iron, lead, and bismuth induced by 107-MeV protons for research and development of accelerator-driven systems

Iwamoto, Hiroki; Nakano, Keita; Meigo, Shinichiro; Satoh, Daiki; Iwamoto, Yosuke; Sugihara, Kenta*; Nishio, Katsuhisa; Ishi, Yoshihiro*; Uesugi, Tomonori*; Kuriyama, Yasutoshi*; et al.

EPJ Web of Conferences, 284, p.01023_1 - 01023_4, 2023/05

 Times Cited Count:0 Percentile:0.00(Nuclear Science & Technology)

For accurate prediction of neutronic characteristics for accelerator-driven systems (ADS) and a source term of spallation neutrons for reactor physics experiments for the ADS at Kyoto University Critical Assembly (KUCA), we have launched an experimental program to measure nuclear data on ADS using the Fixed Field Alternating Gradient (FFAG) accelerator at Kyoto University. As part of this program, the proton-induced double-differential thick-target neutron-yields (TTNYs) and cross-sections (DDXs) for iron, lead, and bismuth have been measured with the time-of-flight (TOF) method. For each measurement, the target was installed in a vacuum chamber on the beamline and bombarded with 107-MeV proton beams accelerated from the FFAG accelerator. Neutrons produced from the targets were detected with stacked, small-sized neutron detectors for several angles from the incident beam direction. The TOF spectra were obtained from the detected signals and the FFAG kicker magnet's logic signals, where gamma-ray events were eliminated by pulse shape discrimination. Finally, the TTNYs and DDXs were obtained from the TOF spectra by relativistic kinematics. The measured TTNYs and DDXs were compared with calculations by the Monte Carlo transport code PHITS with its default physics model of INCL version 4.6 combined with GEM and those with the JENDL-4.0/HE nuclear data library.

Journal Articles

Measurement of 107-MeV proton-induced double-differential thick target neutron yields for Fe, Pb, and Bi using a fixed-field alternating gradient accelerator at Kyoto University

Iwamoto, Hiroki; Nakano, Keita; Meigo, Shinichiro; Satoh, Daiki; Iwamoto, Yosuke; Sugihara, Kenta; Nishio, Katsuhisa; Ishi, Yoshihiro*; Uesugi, Tomonori*; Kuriyama, Yasutoshi*; et al.

Journal of Nuclear Science and Technology, 60(4), p.435 - 449, 2023/04

 Times Cited Count:4 Percentile:40.06(Nuclear Science & Technology)

Double-differential thick target neutron yields (TTNYs) for Fe, Pb, and Bi targets induced by 107-MeV protons were measured using the fixed-field alternating gradient accelerator at Kyoto University for research and development of accelerator-driven systems (ADSs) and fundamental ADS reactor physics research at the Kyoto University Critical Assembly (KUCA). Note that TTNYs were obtained with the time-of-flight method using a neutron detector system comprising eight neutron detectors; each detector has a small NE213 liquid organic scintillator and photomultiplier tube. The TTNYs obtained were compared with calculation results using Monte Carlo-based spallation models (i.e., INCL4.6/GEM, Bertini/GEM, JQMD/GEM, and JQMD/SMM/GEM) and the evaluated high-energy nuclear data library, i.e., JENDL-4.0/HE, implemented in the particle and heavy iontransport code system (PHITS). All models, including JENDL-4.0/HE, failed to predict high-energy peaks at a detector angle of 5$$^{circ}$$. Comparing the energy- and angle-integrated spallation neutron yields at energies of $$le$$20 MeV estimated using the measured TTNYs and the PHITS indicated that INCL4.6/GEM would be suitable for the Monte Carlo transport simulation of ADS reactor physics experiments at the KUCA.

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