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Sugita, Yutaka; Kageyama, Takeshi*; Makino, Hitoshi; Shimbo, Hiroshi*; Hane, Koji*; Kobayashi, Yuichi*; Fujisawa, Yasuo*; Makanae, Koji*; Yabuki, Nobuyoshi*
Proceedings of 17th International Conference on Computing in Civil and Building Engineering (ICCCBE 2018) (Internet), 8 Pages, 2018/06
This paper presents status of development of the iSRE (integrated system for repository engineering) as a design supporting system that enables rational designing of a geological disposal repository. The complimentary technique of construction information modeling/management (CIM) has been employed for the development of iSRE. CIM uses a shared three dimensional (3D) model of associated data through common data models. In this paper, as a design support system that conforms to the characteristics of information management about engineering technology represented by repetition of design during the disposal project period, we examined and designed the function of the "iSRE", constructed a prototype, and confirmed the function through a trial simulating actual work in the disposal project. As a result, with respect to the functions of DB and IF of the iSRE, we got a prospect that these functions can be the foundation of information management on engineering technology, and development of the prototype of the iSRE and its test run extracted issues for practical use of such system.
Chikazawa, Yoshitaka; Kato, Atsushi; Nabeshima, Kunihiko; Otaka, Masahiko; Uzawa, Masayuki*; Ikari, Risako*; Iwasaki, Mikinori*
Proceedings of 23rd International Conference on Nuclear Engineering (ICONE-23) (DVD-ROM), 8 Pages, 2015/05
Design study and evaluation for SDC and safety SDG on the BOP of the demonstration JSFR including fuel handling system, power supply system, component cooling water system, building arrangement are reported. For the fuel handling system, enhancement of storage cooling system has been investigated adding diversified cooling systems. For the power supply, existing emergency power supply system has been reinforced and alternative emergency power supply system is added. For the component cooling system and air conditioning, requirements and relation between safety grade components are investigated. Additionally for the component cooling system, design impact when adding decay heat removal system by sea water has been investigated. For reactor building, over view of evaluation on the external events and design policy for distributed arrangement is reported. Those design study and evaluation provides background information of SDC and SDG.
Oigawa, Hiroyuki; Tsujimoto, Kazufumi; Kikuchi, Kenji; Kurata, Yuji; Sasa, Toshinobu; Umeno, Makoto*; Nishihara, Kenji; Saito, Shigeru; Mizumoto, Motoharu; Takano, Hideki*; et al.
Proceedings of 4th International Workshop on the Utilisation and Reliability of High Power Proton Accelerators, p.325 - 334, 2005/11
The Japan Atomic Energy Research Institute (JAERI) is conducting the research and development (R&D) on the Accelerator-Driven Subcritical System (ADS) for the effective transmutation of minor actinides (MAs). The ADS proposed by JAERI is the 800 MWth, Pb-Bi cooled, tank-type subcritical reactor loaded with (MA+Pu) nitride fuel. The Pb-Bi is also used as the spallation target. In this study, the feasibility of the ADS was discussed with putting the focus on the design around the beam window. The partition wall was placed between the target region and the ductless-type fuel assemblies to keep the good cooling performance for the hot-spot fuel pin. The flow control nozzle was installed to cool the beam window effectively. The thermal-hydraulic analysis showed that the maximum temperature at the outer surface of the beam window could be repressed below 500 
C even in the case of the maximum beam power of 30 MW. The stress caused by the external pressure and the temperature distribution of the beam window was also below the allowable limit.
Tachibana, Yukio; Sawahata, Hiroaki; Iyoku, Tatsuo; Nakazawa, Toshio
Nuclear Engineering and Design, 233(1-3), p.89 - 101, 2004/10
Times Cited Count：10 Percentile：55.63(Nuclear Science & Technology)no abstracts in English
He/ST fusion power reactorShimotono, Hidetoshi*; Nishio, Satoshi; Kondo, Shunsuke*
Fusion Engineering and Design, 69(1-4), p.675 - 681, 2003/09
Times Cited Count：4 Percentile：31.59(Nuclear Science & Technology)The prospect of DHe/ST fusion power reactor have been explored and the design window of the reactor has been specified. The high temperature super-conductor (Bi2212/Ag/Ag) is chosen for TF coils; the operation temperature is 20 K; the conductor current density is about 110 MA/m
at 18-23 T. System analyses have indicated that the design window (which satisfies the constraints HH
2, 
/
1.1, and 
TF800MPa) is amall and require 
1.55, 
40%, and the first wall thermal losd 
1.25 MW/m to ensure the functional and structural reliabilities of the center column (i.e. TF coil system). The plasma current is 75-85 MA.
Sugie, Tatsuo; Costley, A. E.*; Malaquias, A.*; Medvedev, A.*; Walker, C.*
Proceedings of 30th EPS Conference on Controlled Fusion and Plasma Physics (CD-ROM), 4 Pages, 2003/07
The main functions of the Divertor Impurity Monitor are to measure the parameters of impurities and isotopes of hydrogen in the divertor plasmas by using spectroscopic techniques in the wavelength range of 200-1000 nm. This system will have three different types of spectrometers; a) Visible survey spectrometers for impurity species monitoring. b) Filter spectrometers for two-dimensional measurements of particle influxes. c) High dispersion spectrometers for measuring the ion temperature and the particle energy distribution. The divertor region will be observed from the divertor-, the equatorial- and the upper-port. Optical components, such as mirrors, windows etc, mounted close to the plasma will experience higher levels of radiation due to neutron, gamma ray and/or particle irradiations than in present devices. Therefore, the materials of the components have to be carefully selected and mitigating methods adopted where possible. In addition, in-situ and remote calibration methods for diagnostic systems, which will be installed in the strong radiation field, are absolutely essential.
ROSA-V Group
JAERI-Tech 2003-037, 479 Pages, 2003/03
JAERI-Tech-2003-037.pdf:19.25MB
no abstracts in English
Nishihara, Tetsuo; Shimizu, Akira; Tanihira, Masanori*; Uchida, Shoji*
JAERI-Tech 2002-101, 46 Pages, 2003/01
no abstracts in English
Tsutsumi, Masahiro; Oishi, Tetsuya; Kinouchi, Nobuyuki; Sakamoto, Ryuichi; Yoshida, Makoto
Journal of Nuclear Science and Technology, 39(9), p.957 - 963, 2002/09
Times Cited Count：4 Percentile：23.39(Nuclear Science & Technology)An anti-Compton spectrometer with semi-2
Compton suppression is designed to identify the photons emitted from low-level radioactive wastes from radioisotope usage and nuclear research laboratory. Since the objective sample is massive and large, the system has a full opening towards the sample position. The characteristics and features of the system concerning Compton suppression and reduction of the background component due to natural radioactive source are estimated by the Monte Carlo simulations. The anti-Compton technique is shown to be quite advantageous for the reduction of the surrounding natural background radiation, as well as the suppression of the background for the higher energy photons.
Research Committee on Reactor Physics
JAERI-Review 2001-047, 180 Pages, 2002/02
JAERI-Review-2001-047.pdf:10.03MB
Under the Research Committee on Reactor Physics, the Working Party on Reactor Physics of Accelerator-Driven System (ADS-WP) was set in July 1999 to review and investigate special subjects related to reactor physics research for the Accelerator-Driven Subcritical System (ADS).The ADS-WP, at the first meeting, discussed a task guideline of its activity for two years and decided to concentrate upon three subjects: (1) neutron transport calculations in high energy range, (2) static and kinetic (safety-related) characteristics of subcritical system, and (3) system design including ADS concepts and elemental technology developments required.The activity of ADS-WP continued from July 1999 to March 2001. In this duration, the members of ADS-WP met together four times and discussed the above subjects. In addition, the ADS-WP conducted a questionnaire on requests and proposals for the plan of Transmutation Physics Experimental Facility in the High-Intensity Proton Accelerator Project, which is a joint project between JAERI and KEK (High Energy Accelerator Research Organization).This report summarizes the results obtained by the above ADS-WP activity. The report will be useful to overview those results and moreover to set up a new guideline of future research activity in this field.
Adachi, Junichi*; Kaminaga, Masanori; Sasaki, Shinobu; Haga, Katsuhiro; Aso, Tomokazu; Kinoshita, Hidetaka; Hino, Ryutaro
JAERI-Tech 2001-093, 108 Pages, 2002/01
JAERI-Tech-2001-093.pdf:7.49MB
In designing of the neutron scattering facility, a spent target vessel should be replaced with remote handling devices in order to protect radioactive exposure, since it would be highly. In the storage of the spent target vessel, it is necessary to consider decay heat of the target vessel and mercury contamination caused by vaporization of the residual mercury in the vessel. A conceptual design has been carried out to establish basic concept and to clarify its specification of main equipments on a handling and storage system for the spent target vessel. This report presents the basic concept and a system plot plan based on latest design works of remote handling devices, which aim at reasonability and simplification.
Ino, Hiroichi*; Ueta, Shohei; Suzuki, Hiroshi; Tobita, Tsutomu*; Sawa, Kazuhiro
JAERI-Tech 2001-083, 46 Pages, 2002/01
JAERI-Tech-2001-083.pdf:6.31MB
no abstracts in English
Enoeda, Mikio; Ohara, Yoshihiro; Akiba, Masato; Sato, Satoshi; Hatano, Toshihisa; Kosaku, Yasuo; Kuroda, Toshimasa*; Kikuchi, Shigeto*; Yanagi, Yoshihiko*; Konishi, Satoshi; et al.
JAERI-Tech 2001-078, 120 Pages, 2001/12
This report is a summary of the design works, which was discussed in the design workshop held in 2000 for the demonstration (DEMO) blanket aimed to strengthen the commercial competitiveness and technical feasibility simultaneously. The DEMO blanket must supply the feasibility and experience of the total design of the power plant and the materials. This conceptual design study was performed to determine the updated strategy and goal of the R&D of the DEMO blanket which applies the supercritical water cooling proposed in A-SSTR, taking into account the recent progress of the plasma research and reactor engineering technology.
Nishihara, Tetsuo; Muto, Yasushi; Uchida, Shoji*; Yoshioka, Naoki*
JAERI-Tech 2001-077, 44 Pages, 2001/12
JAERI-Tech-2001-077.pdf:2.16MB
JAERI has conducted the feasibility study of the HTGR gas turbine system from 1996 to 2000 sponsored by MEXT. This report concludes the safety criteria and rationalization of the safety items in the HTGR system.With respect to the safety criteria, the same value for the LWR is selected as the limit of radiation exposure. Probability of the design basis event (DBE) and beyond design basis event (BDBE) is set lower than those for the LWR to get higher safety margin. Adequate initial events and mitigation system are selected to consider the event sequence. The concept of the probability analysis is applied to identify DBEs and BDBEs. It is found that some safety items can be rationalized in consideration of the safety features of the HTGR. Finally, the safety class and design category of the items in the HGTR-GT are classified.
Nishihara, Tetsuo; Shiozawa, Shusaku; Ogawa, Masuro
IAEA-TECDOC-1236, p.11 - 25, 2001/08
Design and evaluation of heat utilization systems for the high temperature engineering test reactor was carried out as the Coordinated Research Program in the IAEA from 1994 to 1999. The final technical document was published as the TECDOC. The chapter 3, outline of the HTTR, and section 5.2.1, Japanese process design to steam reforming of methane for hydrogen production, were written by JAERI.
Nishihara, Tetsuo; Hada, Kazuhiko
Nihon Genshiryoku Gakkai-Shi, 41(5), p.571 - 578, 1999/05
Times Cited Count：5 Percentile：40.62(Nuclear Science & Technology)no abstracts in English
Inagaki, Yoshiyuki; Hada, Kazuhiko; Nishihara, Tetsuo; Takeda, Tetsuaki; Hino, Ryutaro; Haga, Katsuhiro
JAERI-Tech 97-050, 125 Pages, 1997/10
no abstracts in English
Nishihara, Tetsuo; Hada, Kazuhiko; Shiozawa, Shusaku
JAERI-Research 97-022, 110 Pages, 1997/03
JAERI-Research-97-022.pdf:4.1MB
no abstracts in English
Murao, Yoshio; Ochiai, Masaaki
Eighth Int. Topical Meeting on Nuclear Reactor Thermal-Hydraulics (NURETH-8), 2, p.1075 - 1085, 1997/00
no abstracts in English
Sugie, Tatsuo; Ogawa, Hiroaki; *; *; Ando, Toshiro; Kasai, Satoshi
JAERI-Tech 96-055, 82 Pages, 1996/12
no abstracts in English
