Otsuka, Yusuke*; Kanazawa, Naoya*; Hirayama, Motoaki*; Matsui, Akira*; Nomoto, Takuya*; Arita, Ryotaro*; Nakajima, Taro*; Hanashima, Takayasu*; Ukleev, V.*; Aoki, Hiroyuki; et al.
Science Advances (Internet), 7(47), p.eabj0498_1 - eabj0498_9, 2021/11
Oshikawa, Takumi*; Funakoshi, Yoshihiko*; Imaoka, Hiroshi*; Yoshikawa, Kohei*; Maari, Yasutaka*; Iguchi, Masahide; Sakurai, Takeru; Nakahira, Masataka; Koizumi, Norikiyo; Nakajima, Hideo
Proceedings of 19th International Forgemasters Meeting (IFM 2014), p.254 - 259, 2014/09
ITER is a large-scale experiment that aims to demonstrate that it is possible to produce commercial energy from fusion. ITER Toroidal Field Coil Case (hereinafter referred to as "ITER TFCC") is one of the important components of ITER. The ITER TFCC materials are made of high nitrogen austenitic stainless steel and having various configurations. The ITER TFCC material which manufactured by JCFC has a complex configuration with heaver thickness than other materials. It is difficult to form near net shape to delivery configuration by ordinary open die forging method such as upset and stretching, because the ITER TFCC materials manufactured by JCFC have a complex configuration. Therefore ingot weight and lead time of machining increase when ITER TFCC materials are forged by ordinary open die forging method. Moreover, in order to get good attenuation at Ultrasonic examination, it is necessarily to make fine and uniform grain of the material. However, it is impossible to control grain size of austenitic stainless steel by heat treatment. The grain becomes fine and uniform by only forging process with suitable condition. Therefore, JCFC has studied suitable forging method to become near net shape to delivery configuration and also to get fine grain of center of the material. Based on these result, ITER TFCC materials were manufactured. This innovative forging process led to reduce the weight of ingot compared with general forging. And it had good Ultrasonic attenuation. It was confirmed that the results of material test and nondestructive examination satisfied the requirements of Japan domestic agency (hereinafter referred to as "JADA"). Moreover, the test coupons were taken from center of thick part of product and used for various tests. As the result of tests, it was confirmed that results of material test satisfied the requirements of JADA. It is clear that this innovative forging method is very suitable process for manufacturing of ITER TFCC materials.
Nabara, Yoshihiro; Nunoya, Yoshihiko; Isono, Takaaki; Hamada, Kazuya; Uno, Yasuhiro; Takahashi, Yoshikazu; Nakajima, Hideo; Tsuzuku, Seiji*; Tagawa, Kohei*; Miyashita, Katsumi*; et al.
Teion Kogaku, 47(3), p.140 - 146, 2012/03
no abstracts in English
Kim, G.; Nakajima, Kohei*; Teshima, Naoya*; Tatekawa, Takayuki; Suzuki, Yoshio; Takemiya, Hiroshi
Progress in Nuclear Science and Technology (Internet), 2, p.634 - 638, 2011/10
We developed grid-enabled application of full-scale 3D vibration simulator for an entire nuclear power plant on simple orchestration application framework (SOAF). The simulator is an analysis system to study seismic response of a whole digitalized nuclear power plant. In the simulator, components of a power plant are treated in hierarchical manner so that large components are grouped at primary level and small components such as pipes at secondary level. Boundary condition data are transferred from the primary level to the secondary level. SOAF provides functionality to enable users to simply define the data transfer in pipelined scenario which is technically difficult to realize using the existing grid technology. In this paper, we discuss technical issues of the realization of pipelined scenario on grid and demonstrate effectiveness of SOAF by analysis of High Temperature Engineering Test Reactor of JAEA using grid-enabled application implementing SOAF.
Kim, G.; Nakajima, Kohei*; Teshima, Naoya; Tatekawa, Takayuki; Suzuki, Yoshio; Takemiya, Hiroshi
Proceedings of Joint International Conference of 7th Supercomputing in Nuclear Application and 3rd Monte Carlo (SNA + MC 2010) (USB Flash Drive), 5 Pages, 2010/10
Full-Scale 3D vibration simulator for an entire nuclear power plant is a seismic response analysis system for a whole digitalized nuclear power plant. In the system, boundary data from large components are used as input data of small components. To make a whole simulation efficient, we introduced pipeline method in which the data were transferred each time step running all components simulations in parallel. In the realization of the method on grid, since there were no existing grid technologies to sufficiently support the method for a long time, we developed simple orchestration application framework (SOAF) and using the SOAF, we performed seismic response analysis of a test reactor of JAEA and succeeded simulation for a week.
Tatekawa, Takayuki; Nakajima, Kohei*; Kim, G.; Teshima, Naoya; Suzuki, Yoshio; Takemiya, Hiroshi
High Performance Computing on Vector Systems 2010, p.107 - 120, 2010/09
In the atomic field, by integrating various simulation codes which were installed on distributed computers, large-scale and detailed simulations which aim explication of complicated phenomena. However integration of each simulation codes and cooperative operation of the integrated codes make heavy burden for researchers. We have developed the Simple Orchestration Application Framework (SOAF) to cooperatively control simulation codes on remote computers from a client PC. SOAF enables researchers to cooperatively execute various codes on grid infrastructure by only describing a configuration file including the information of execution codes and file flows among them. SOAF does not need substantial modification of the simulation codes. By using SOAF, we successfully execute four plasma simulation codes included in the "Burning Plasma Integrated Code" according to the scenario described in the configuration file.
Tatekawa, Takayuki; Nakajima, Kohei*; Teshima, Naoya; Kim, G.; Suzuki, Yoshio; Takemiya, Hiroshi; Hayashi, Nobuhiko; Iba, Katsuyuki*
Proceedings of 3rd International Joint Conference on Computational Sciences and Optimization (CSO 2010), p.322 - 326, 2010/05
Tatekawa, Takayuki; Nakajima, Kohei*; Kim, G.; Kino, Chiaki; Teshima, Naoya; Suzuki, Yoshio; Takemiya, Hiroshi
FUJITSU Famirikai Rombunshu (Internet), 19 Pages, 2010/03
We have introduced about the framework to make the integration of large and complicated simulation such as a proof strength simulation of nuclear power plants and a control simulation of nuclear fusion plasma which codes are installed to distributed computers. We able to carry out detailed simulations by integrating various simulation methods with development of simulation technique. However it becomes a burden to control the integration of each simulation code for researchers. We have noticed that the execution scenarios of each code in cooperated simulation are roughly categorized to workflow type, pipeline type, and conditional branch type. Then we have developed the framework in which just write those patterns in a configuration file and achieve the cooperative execution of element codes without substantial modification of simulation codes.
Miyamura, Hiroko; Nakajima, Kohei*; Suzuki, Yoshio; Hayashi, Sachiko; Takemiya, Hiroshi; Nakajima, Norihiro
Zen NEC C&C Shisutemu Yuza Kai Heisei-21-Nendo Rombunshu (CD-ROM), 12 Pages, 2010/02
In this paper, we propose data exploration system for the evaluation of numerical simulation results. With the improvement in the performance of supercomputers, numerical simulations have become larger and more complex, which has made the interpretation of simulation results more difficult. Moreover, occasionally, users cannot evaluate numerical simulation results, even though they have spent a great deal of time, because interactive visualization is impossible for such large-scale data. Therefore, we herein propose a data exploration system with which users evaluate large-scale time-series data that has been obtained in a parallel and distributed environment. The proposed system allows users to simultaneously visualize and analyze data in both the global and local scales.
Nakajima, Kohei; Suzuki, Yoshio; Teshima, Naoya; Sugimoto, Shinichiro*; Yoshimura, Shinobu*; Nakajima, Norihiro
Zen NEC C&C Shisutemu Yuza Kai Heisei-20-Nendo Rombunshu (CD-ROM), 13 Pages, 2009/02
Grid computing environment is equipped with a lot of tools to manage jobs and computers. Thereby, user can use the computers without directly access. However, user has to acquire usage of these tools even when user does an easy job because all usages of these tools are peculiar to the grid base. A lot of users think that the grid is difficult even though these tools exist. Then, we developed script generator API to make the job script. These settings were made easy by this API in the user application. In this paper, the outline of this API and the adjustment to the application are described.
Suzuki, Yoshio; Kushida, Noriyuki; Teshima, Naoya; Nakajima, Kohei; Nishida, Akemi; Nakajima, Norihiro
High Performance Computing on Vector Systems 2008, p.65 - 77, 2009/00
Center for computational science and e-systems, Japan Atomic Energy Agency (CCSE/JAEA) has been carrying out R&Ds of grid computing technology since FY1995 aiming at establishing an infrastructure for the computational science research. One of them is R&D of IT-Based Laboratory (ITBL) infrastructure. The ITBL project is a national project placed as one of the e-Japan Priority Policy Program to realize the e-Japan Strategy. By succeeding the technology of ITBL infrastructure, CCSE is carrying out R&D of Atomic Energy Grid Infrastructure (AEGIS) to construct an intelligent infrastructure for the atomic energy research. CCSE has been carrying out international cooperation researches in various fields to advance computer science and to expand AEGIS grid computing environment. To achieve this, we have developed the system to construct interoperable environments between AEGIS and other grid middleware.
Suzuki, Yoshio; Nishida, Akemi; Araya, Fumimasa; Kushida, Noriyuki; Akutsu, Taku; Teshima, Naoya; Nakajima, Kohei; Kondo, Makoto; Hayashi, Sachiko; Aoyagi, Tetsuo; et al.
Journal of Power and Energy Systems (Internet), 3(1), p.60 - 71, 2009/00
Center for computational science and e-systems of Japan Atomic Energy Agency is carrying out R&D in the area of extra large-scale simulation technologies for solving nuclear plant structures in its entirety. Specifically, we focus on establishing a virtual plant vibration simulator on inter-connected supercomputers intended for seismic response analysis of a whole nuclear plant. The simulation of a whole plant is a very difficult task because an extremely large dataset must be processed. To overcome this difficulty, we have proposed and implemented a necessary simulation framework and computing platform. The computing platform enables an extra large-scale whole nuclear plant simulation to be carried out on a grid computing platform ITBL-IS and AEGIS. The simulation framework based on the computing platform has been applied to a linear elastic analysis of the reactor pressure vessel and cooling systems of the nuclear research facility, HTTR.
Nakajima, Norihiro; Araya, Fumimasa; Suzuki, Yoshio; Nishida, Akemi; Matsubara, Hitoshi; Nakajima, Kohei
Dai-27-Kai Nihon Shimyureshon Gakkai Taikai Happyo Rombunshu, p.511 - 514, 2008/06
A real space simulator for vibration table targeted to a nuclear power station has been proposed, which generates over tera-byte amount of calculated result. In order to analyze a huge size data, a data analyzer and data analyzing monitor system is suggested in this paper. A result of finite element analysis is examined by the system taking into account relation among neighboring elements' results. It is operated by multi-monitoring to view analyzing process. The system is implemented on a grid computing environment, AEGIS (atomic energy grid infrastructure) with coupling a large data visualization system.
Suzuki, Yoshio; Nakajima, Norihiro; Araya, Fumimasa; Hazama, Osamu; Nishida, Akemi; Kushida, Noriyuki; Akutsu, Taku; Teshima, Naoya; Nakajima, Kohei; Kondo, Makoto; et al.
Proceedings of 16th International Conference on Nuclear Engineering (ICONE-16) (CD-ROM), 9 Pages, 2008/05
Suzuki, Yoshio; Nakajima, Kohei; Kushida, Noriyuki; Kino, Chiaki; Aoyagi, Tetsuo; Nakajima, Norihiro; Iba, Katsuyuki*; Hayashi, Nobuhiko; Ozeki, Takahisa; Totsuka, Toshiyuki; et al.
Fusion Engineering and Design, 83(2-3), p.511 - 515, 2008/04
In collaboration with the Naka Fusion Institute of Japan Atomic Energy Agency (NFI/JAEA) and the National Institute for Fusion Science of National Institute of Natural Science (NIFS/NINS), Center for Computational Science and E-systems of Japan Atomic Energy Agency (CCSE/JAEA) aims at establishing an integrated framework for experiments and analyses in nuclear fusion research based on the Atomic Energy Grid InfraStructure (AEGIS). AEGIS has been being developed by CCSE/JAEA aiming at providing the infrastructure that enables atomic energy researchers in remote locations to carry out R&D efficiently and collaboratively through the Internet. Toward establishing the integrated framework, we have been applying AEGIS to pre-existing three systems.
Harada, Akio; Sato, Tadashi*; Nakajima, Kunihisa; Komuro, Yuichi; Shiraishi, Hirotsugu*; Hattori, Takamitsu; Ikuta, Yuko; Yachi, Shigeyasu; Kushita, Kohei
JAERI-Review 2005-026, 55 Pages, 2005/09
This report provides an example of answers to the problems of the 37th Examination for the Chief Engineer of Nuclear Fuel. This examination was done as a national qualification in March 2005. Brief explanations or references are added to some answers.
Yachi, Shigeyasu; Nakamura, Jinichi; Amaya, Masaki; Nakajima, Kunihisa; Komuro, Yuichi; Nakajima, Katsuaki*; Kobayashi, Yasuhiko; Sato, Tadashi*; Suga, Shinichi*; Noguchi, Hiroshi; et al.
JAERI-Review 2004-020, 61 Pages, 2004/09
This report provides an example of answers to the problems of the 36th Examination for the Chief Engineer of Nuclear Fuel. This examination was done as a national qualification in March 2004. Brief explanations or references are added to some answers.
Yachi, Shigeyasu; Sato, Tadashi; Suga, Shinichi*; Komuro, Yuichi; Uchida, Masaaki; Nakajima, Kunihisa; Nakamura, Jinichi; Amezawa, Hiroo; Omura, Hideaki*; Minato, Kazuo; et al.
JAERI-Review 2003-025, 162 Pages, 2003/09
The report contains example of answers to the Problems of 31st(1999) to 35th(2003) Examinations for the Chief Engineer of Nuclear Fuel which were conducted as a national qualification examination. Brief explanations or references are given to some answers.
Suzuki, Yoshio; Matsumoto, Nobuko; Nakajima, Kohei; Tani, Masayuki; Nakajima, Norihiro
no journal, ,
no abstracts in English
Suzuki, Yoshio; Kushida, Noriyuki; Yamagishi, Nobuhiro; Minami, Takahiro; Matsumoto, Nobuko; Nakajima, Kohei; Nishida, Akemi; Matsubara, Hitoshi; Tian, R.; Hazama, Osamu; et al.
no journal, ,
no abstracts in English