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

https://doi.org/10.1051/epjconf/202430203002

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.

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.

Gas-liquid two-phase flow analysis using multi-phase field method

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

Dai-36-Kai Suchi Ryutai Rikigaku Shimpojiumu Koen Rombunshu (Internet), 5 Pages, 2022/12

The conventional Allen-Cahn type multi-phase field method was modified to conserve not only the sum of the masses of all phases but also the mass of each phase. The interface advection calculations within a two-dimensional rotational velocity field were performed as a verification problem, and the conservation was successfully achieved. The proposed method was used to calculate the horizontally aligned pair of bubbles rising, and it was found that the bouncing phenomenon between bubbles can be calculated at 1/50 resolution of the high-resolution calculation by Zhang et al. using the volume of fluid method.

Evaluation on laser quenching heat transfer mechanism using numerical method and improvement of quenching depth

Kitagawa, Yoshihiro; Shirahama, Takuma*; Kisohara, Naoyuki; Tsuboi, Akihiko

Dai-96-Kai Reza Kako Gakkai Koen Rombunshu (Internet), p.91 - 96, 2022/01

Laser scanning quenching is a locally and rapidly heat-treated process and has an advantage of no coolant required. Compared with conventional technique such as induction quenching, the region of laser quenching is about 0.50.7mm in depth and it needs to be expanded for more applications or durability. For this purpose, the temperature distributions and transitions in materials during laser irradiation have been revealed by using a 3D heat transfer computer code, micro-structural observation and hardness transitions in depth direction. The results indicate the laser irradiation with low power and low scan speed condition allows deeper quenching area, but it also suggests the hardness of the deepest quenching area is degraded due to slow temperature decreasing rate after laser heat scanning. Multiple times continuous irradiation have been proposed and studied to resolve this hardness degradation, and maximum quenching depth of 1.4mm is obtained under three times irradiation and controlling its power and scan speed properly.

Maximizing by tuning nematicity and magnetism in FeSeS superconductors

Matsuura, Kohei*; Mizukami, Yuta*; Arai, Yuki*; Sugimura, Yuichi*; Maejima, Naoyuki*; Machida, Akihiko*; Watanuki, Tetsu*; Fukuda, Tatsuo; Yajima, Takeshi*; Hiroi, Zenji*; et al.

Nature Communications (Internet), 8, p.1143_1 - 1143_6, 2017/10

https://doi.org/10.1038/s41467-017-01277-x

Preliminary conceptual design of the secondary sodium circuit-eliminated JSFR (Japan Sodium Fast Reactor) adopting a supercritical CO turbine system, 2; Turbine system and plant size

Kisohara, Naoyuki; Sakamoto, Yoshihiko; Kotake, Shoji*

JAEA-Research 2014-016, 60 Pages, 2014/09

JAEA-Research-2014-016.pdf:22.38MB

JAEA has performed a design study of an S-CO gas turbine system applied to the JSFR. In this study, the S-CO cycle turbine system was directly connected to the primary sodium system of the JSFR to eliminate the secondary sodium circuit, aiming for further economical improvement. This report describes the system configuration, heat/mass balance, and main components of the S-CO turbine system, based on the JSFR specifications. The layout of components and piping in the reactor and turbine buildings were examined and the dimensions of the buildings were estimated. The study has revealed that the reactor and turbine buildings could be reduced by 7% and 40%, respectively, in comparison with those in the existing JSFR design with the secondary sodium circuit employing the steam turbine. The cycle thermal was also calculated as 41.9-42.3%, which is nearly the same as that of the JSFR with the water/steam system.

ELM triggering by energetic particle driven mode in wall-stabilized high- plasmas

Matsunaga, Go; Aiba, Nobuyuki; Shinohara, Koji; Asakura, Nobuyuki; Isayama, Akihiko; Oyama, Naoyuki; JT-60 Team

Nuclear Fusion, 53(7), p.073046_1 - 073046_9, 2013/06

https://doi.org/10.1088/0029-5515/53/7/073046

Effects of local toroidal field ripple due to test blanket modules for ITER on radial transport of thermal ions

Oyama, Naoyuki; Urano, Hajime; Shinohara, Koji; Honda, Mitsuru; Takizuka, Tomonori; Hayashi, Nobuhiko; Kamada, Yutaka; JT-60 Team

Nuclear Fusion, 52(11), p.114013_1 - 114013_9, 2012/11

https://doi.org/10.1088/0029-5515/52/11/114013

Effects of local toroidal field (TF) ripple due to test blanket modules (TBMs) for ITER on radial transport of thermal ions are investigated using fully three-dimensional magnetic field orbit following Monte Carlo (F3D-OFMC) code. The simulation under ITER plasma condition indicates that the additional losses caused by the localized TF ripple due to TBMs linearly increase with number of TBMs. When the amplitude of local TF ripple in one TBM port is increased, on the other hand, the additional losses increase quickly. A comparison of the number of lost particles suggests that a condition with three TBM ports corresponds to 1.7 times of ripple amplitude at one TBM port.

Evaluation of Earthquake and Tsunami on JSFR

Chikazawa, Yoshitaka; Enuma, Yasuhiro; Kisohara, Naoyuki; Yamano, Hidemasa; Kubo, Shigenobu; Hayafune, Hiroki; Sagawa, Hiroshi*; Okamura, Shigeki*; Shimakawa, Yoshio*

Proceedings of 2012 International Congress on Advances in Nuclear Power Plants (ICAPP '12) (CD-ROM), p.677 - 686, 2012/06

Evaluation of Earthquake and Tsunami on JSFR has been analyzed. For seismic design, safety components are confirmed to maintain their functions even against recent strong Earthquakes. As for Tsunami, some parts of reactor building might be submerged including component cooling water system whose final heat sink is sea water. However, in the JSFR design, safety grade components are independent from component cooling water system (CCWS). The JSFR emergency power supply adopts a gas turbine system with air cooling, since JSFR does not basically require quick start-up of the emergency power supply thanks to the natural convection DHRS. Even in case of long station blackout, the DHRS could be activated by emergency batteries or manually and be operated continuously by natural convection.

Edge pedestal characteristics in JET and JT-60U tokamaks under variable toroidal field ripple

Urano, Hajime; Saibene, G.*; Oyama, Naoyuki; Parail, V.*; de Vries, P.*; Sartori, R.*; Kamada, Yutaka; Kamiya, Kensaku; Loarte, A.*; Lnnroth, J.*; et al.

Nuclear Fusion, 51(11), p.113004_1 - 113004_10, 2011/11

https://doi.org/10.1088/0029-5515/51/11/113004

The effect of TF ripple on the edge pedestal characteristics are examined in JET and JT-60U. By the installation of ferritic inserts, TF ripple was reduced from to in JT-60U. In JET, TF ripple was varied from to by feeding different currents to TF coils. The pedestal pressure was similar with reduced ripple in JT-60U. In JET, no clear difference of the pedestal characteristics was also observed. The edge toroidal rotation clearly decreased in counter direction by increased TF ripple. However, in JT-60U, the ELM frequency decreased by and the increased ELM loss power by with reduced ripple. In JET, ELM frequency increases only slightly with increased TF ripple. From this inter-machine experiment, TF ripple less than does not strongly affect the pedestal pressure. The effect of TF ripple on pedestal characteristics at lower collisionality close to ITER should be investigated as a next step study.