Photonuclear reaction cross-section evaluation of Ta and Bi considering experimental double differential cross-section data

Nguyen, T. T. H.*; Iwamoto, Nobuyuki; Sanami, Toshiya*

EPJ Web of Conferences, 322, p.10004_1 - 10004_3, 2025/03

https://doi.org/10.1051/epjconf/202532210004

Extension of particle-based in-situ visualization for multipoint VR visualization

Kawamura, Takuma; Shimomura, Kazuya; Osaki, Tsukasa*; Idomura, Yasuhiro

EPJ Web of Conferences, 302, p.11002_1 - 11002_8, 2024/10

https://doi.org/10.1051/epjconf/202430211002

In the field of nuclear engineering, complex simulations on exa-scale supercomputers generate large-scale data. To facilitate efficient analysis of such simulation data, one needs to share them among scientists at remote locations. However, data I/O and data transfer for such large-scale data are quite costly. To resolve these issues, we developed a remote in-situ visualization system IS-PBVR based on the particle-based volume rendering (PBVR), which is suitable for parallel processing on modern supercomputers. In this study, we extend IS-PBVR for VR visualization on multiple client PCs, thus developing a multi-point remote VR visualization. We apply this technique to fluid simulations on GPU-based supercomputers and verify its utility by sharing in-situ VR visualization between multiple client PCs.

GPU-enabled ensemble data assimilation for mesh-refined lattice Boltzmann method

Hasegawa, Yuta; Idomura, Yasuhiro; Onodera, Naoyuki

EPJ Web of Conferences, 302, p.03005_1 - 03005_9, 2024/10

https://doi.org/10.1051/epjconf/202430203005

We implemented the ensemble data assimilation (DA) method, the local ensemble transform Kalman filter (LETKF), into the mesh-refined lattice Boltzmann method (LBM) for turbulent flows. Both the LETKF and the mesh-refined LBM were fully implemented on GPUs, so that they are efficiently computed on modern GPU-based supercomputers. We examined the DA accuracy against the flow around a cylinder. The result showed that our method enabled accurate DA with spatially- and temporarily-sparse observation data; the error of the assimilated velocity field with the observation interval of and the observation resolution (1.56% of the total computational grids) was smaller than the amplitude of the observation noise, where is the period of the Krmn vortex and is diameter of the square cylinder.

Implementation of track length estimator for flux distribution tallies using proper orthogonal decomposition in one-dimensional geometry

Kondo, Ryoichi; Endo, Tomohiro*; Yamamoto, Akio*

EPJ Web of Conferences, 302, p.04002_1 - 04002_10, 2024/10

https://doi.org/10.1051/epjconf/202430204002

In the recent study, we have developed an efficient flux distribution tallying method in the Monte Carlo calculation toward the high-fidelity, large scale multi-physics simulation. In this method, the proper orthogonal decomposition is applied to the flux distribution tallies. While the tallying method was implemented with the collision estimator in the previous study, the track length estimator is implemented in the present study to obtain the tally with lower statistical error. The implementation of the flux distribution tally with the track length estimator is compared with that of the collision estimator and the normal track length estimator in a one-dimensional problem. The numerical results reveal that the distribution tally using the POD with the track length estimator can obtain a more precise solution compared with that with the collision estimator. Therefore, in terms of the statistical error, the relationship between the distribution tally with track length and collision estimator is similar to that between the conventional track length and collision estimators.

Intriguing aspects of light baryon resonances

Khemchandani, K. P.*; Martnez Torres, A.*; Kim, S.-H.*; Nam, S.-I.*; Hosaka, Atsushi; Nagahiro, Hideko*

EPJ Web of Conferences, 301, p.03001_1 - 03001_10, 2024/08

https://doi.org/10.1051/epjconf/202430103001

no abstracts in English

Evaluation of thermal neutron scattering law of nuclear-grade isotropic graphite

Nakayama, Shinsuke; Iwamoto, Osamu; Kimura, Atsushi

EPJ Web of Conferences, 294, p.07001_1 - 07001_6, 2024/04

https://doi.org/10.1051/epjconf/202429407001

Graphite is a candidate of moderator in innovative nuclear reactors such as molten salt reactors. Scattering of thermal neutrons by the moderator material has a significant impact on the reactor core design. To contribute to the development of innovative nuclear reactors, an evaluation method of thermal neutron scattering law for reactor grade graphite was studied. The inelastic scattering component due to lattice vibration was evaluated based on the phonon density of states computed with first-principles lattice dynamics simulations. The simulations were performed for ideal crystalline graphite. The coherent elastic scattering component due to crystal structure was evaluated based on neutron transmission and scattering experiments recently performed in the J-PARC/MLF facility. In comparison with the neutron transmission experiments, it was found that the quantification of small-angle neutron scattering due to structures larger than crystal, such as pores in graphite, is important. Based on the above methods, thermal neutron scattering law data for reactor-grade graphite at room temperature were evaluated.

Nuclide production cross sections in proton-induced reactions on Bi at GeV energies

Iwamoto, Hiroki; Nakano, Keita*; Meigo, Shinichiro; Takeshita, Hayato; Maekawa, Fujio

EPJ Web of Conferences, 284, p.01033_1 - 01033_4, 2023/05

https://doi.org/10.1051/epjconf/202328401033

no abstracts in English

Evaluation of light-element reactions in the resolved resonance region

Dimitriou, P.*; Chen, Z.*; deBoer, R. J.*; Hale, G.*; Kunieda, Satoshi; Leeb, H.*; Paris, M.*; Pigni, M. T.*; Srdinko, Th.*; Tamagno, P.*; et al.

EPJ Web of Conferences, 284, p.03002_1 - 03002_5, 2023/05

https://doi.org/10.1051/epjconf/202328403002

Charged-particle-induced reactions at low energies in the resolved resonance region are important for applications such as ion beam analysis of materials and management of the nuclear fuels. However, the evaluated nuclear data libraries maintained by national or international coordinated efforts (ENDF, JEFF, JENDL, CENDL) are to date, incomplete as far as charged-particle- induced reactions in the resolved resonance region are concerned. The IAEA Nuclear Data Section is coordinating an international effort to (i) verify that the existing R-matrix codes are consistent, (ii) evaluate charged-particle cross sections in the resolved resonance region, (iii) produce evaluated nuclear data files for further processing and finally (iv) disseminate the evaluated data through general purpose evaluated nuclear data libraries. We present the results of the effort made thus far on (1) verification of the available R-matrix codes, minimization methods and calculation of covariances, (2) the evaluation of the compound system Be*, and (3) improving reaction data for the applications.

Analyses of JAEA/FNS iron in-situ experiment with latest nuclear data libraries

Konno, Chikara; Kwon, Saerom*

EPJ Web of Conferences, 284, p.15010_1 - 15010_4, 2023/05

https://doi.org/10.1051/epjconf/202328415010

For the JENDL development we analyzed the iron in-situ experiment at the DT neutron source facility FNS in JAEA with the two-dimensional Sn code DORT and the latest nuclear data libraries: JENDL-4.0, ENDF/B-VIII.0 and JEFF-3.3. As a result, we found that the result with ENDF/B-VIII.0 reproduced the measured data worse than those with JENDL-4.0 and JEFF-3.3 as follows: overestimation of neutron flux below a few keV, underestimation of the reaction rate of In(n,n')In sensitive to neutrons above 0.3 MeV and underestimation of neutron flux above 10 MeV. Our detailed study specified that the inelastic scattering cross section of Fe-56 in ENDF/B-VIII.0 mainly caused the overestimation of neutron flux below a few keV and underestimation of the reaction rate of In(n,n')In and that the angular distribution data of the elastic scattering and the cross section of the (n,2n) reaction of Fe in ENDF/B-VIII.0 were the reason of the underestimation of neutron flux above 10 MeV.

Measurement of displacement cross-sections of Nb irradiated by protons with kinetic energy range between 0.4 and 3 GeV

Meigo, Shinichiro; Nakano, Keita*; Matsuda, Hiroki; Iwamoto, Yosuke; Yoshida, Makoto*

EPJ Web of Conferences, 284, p.05001_1 - 05001_4, 2023/05

https://doi.org/10.1051/epjconf/202328405001

In high-intensity proton accelerator facilities such as Accelerator Driven System (ADS) and the spallation neutron source, it is crucial to evaluate the damage of beam-interception materials and accelerator components, such as a magnet coil. The displacement per atom (dpa) is used as a damage index, which is derived by integrating the particle flux and the displacement cross section based on the NRT model. Although the dpa is employed as the standard, the experimental data of displacement cross section are scarce for a proton in the energy region above 20 MeV. To obtain the data for superconducting materials for high-intensity accelerators and magnets, the displacement cross section of Nb for proton irradiation with a kinetic energy range between 0.4 and 3 GeV was measured. For sustaining damage in the sample, the Nb sample was cooled at a cryogenic temperature (8 K), where the recombination of Frenkel pairs due to thermal motion was well suppressed with maintaining the normal conductivity to maintain Matthiessen's rule. The displacement cross section of Nb was calculated using the PHITS code, and was compared with the present experimental results. It was found that the widely utilized NRT model overestimates the cross section by a factor of 2, as suggested by the previous works. It was also found that the calculation with a recently proposed athermal recombination corrected (arc) model based on Molecular Dynamics (MD) shows good agreement with the present data.