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JAEA Reports

Annual report of Nuclear Emergency Assistance and Training Center (April 1, 2010 - March 31, 2011)

Katagiri, Hiromi; Okuno, Hiroshi; Sawahata, Masayoshi; Ikeda, Takeshi; Sato, Sohei; Terakado, Naoya; Nagakura, Tomohiro; Nakanishi, Chika; Fukumoto, Masahiro; Yamamoto, Kazuya; et al.

JAEA-Review 2011-037, 66 Pages, 2011/12

JAEA-Review-2011-037.pdf:4.52MB

When a Nuclear emergency occurs, Nuclear Emergency Assistance & Training Center (NEAT) of JAEA gives technical advice and information, dispatch specialists as required, supplies emergency equipment and materials to the National Government and local governments. NEAT provides various lectures and training courses concerning nuclear disaster prevention for those personnel taking an active part in emergency response organizations at normal time. NEAT also researches on nuclear disaster prevention and cooperates with international organizations. Concerning about the assistance to the Accident of Fukushima No.1 Nuclear Power Station caused by the Great East Japan Earthquake at 11 March, 2011, JAEA assisted activities including environmental radiation monitoring, environmental radioactivity analyses, resident public consulting etc., with its full scale effort. NEAT served as the center of these supporting activities of JAEA.

JAEA Reports

Annual report of Nuclear Emergency Assistance and Training Center (April 1, 2009 - March 31, 2010)

Kanamori, Masashi; Shirakawa, Yusuke; Yamashita, Toshiyuki; Okuno, Hiroshi; Terunuma, Hiroshi; Ikeda, Takeshi; Sato, Sohei; Terakado, Naoya; Nagakura, Tomohiro; Fukumoto, Masahiro; et al.

JAEA-Review 2010-037, 60 Pages, 2010/09

JAEA-Review-2010-037.pdf:3.11MB

When a nuclear emergency occurs in Japan, the Japan Atomic Energy Agency (JAEA) provides technical support to the National government, local governments, police, fire station and license holder etc. They are designated public organizations conforming to the basic law on emergency preparedness and the basic plan for disaster countermeasures. The Nuclear Emergency Assistance & Training Center (NEAT) of JAEA provides a comprehensive range of technical support activities to an off-site center in case of a nuclear emergency. Specifically, NEAT gives technical advice and information, provides for the dispatch of specialist as required, supplies emergency equipments and materials to the national government and municipal office. NEAT provide various lectures and training course concerning nuclear disaster prevention for those personnel taking an active part in emergency response organizations at normal time. And NEAT researches on nuclear disaster prevention and also cooperate with international organizations. This annual report summarized the activities of JAEA/NEAT in the fiscal year 2009.

JAEA Reports

Annual report of Nuclear Emergency Assistance and Training Center (April 1, 2008 - March 31, 2009)

Kanamori, Masashi; Hashimoto, Kazuichiro; Terunuma, Hiroshi; Ikeda, Takeshi; Omura, Akiko; Terakado, Naoya; Nagakura, Tomohiro; Fukumoto, Masahiro; Watanabe, Fumitaka; Yamamoto, Kazuya; et al.

JAEA-Review 2009-023, 61 Pages, 2009/09

JAEA-Review-2009-023.pdf:8.49MB

When a nuclear emergency occurs in Japan, the Japan Atomic Energy Agency (JAEA) provides technical support to the National government, local governments, police, fire station and license holder etc. They are Designated Public Organizations conforming to the Basic Law on Emergency Preparedness and the Basic Plan for Disaster Countermeasures. The Nuclear Emergency Assistance and Training Center (NEAT) of JAEA provides a comprehensive range of technical support activities to an Off-Site Center in case of a nuclear emergency. Specifically, NEAT gives technical advice and information, provides for the dispatch of specialist as required, supplies emergency equipments and materials to the Joint Council of Nuclear Disaster Countermeasures, which meets at the Off-Site Center. NEAT provide various lectures and training course concerning nuclear disaster prevention for those personnel taking an active part in emergency response organizations at normal time. And NEAT researches on nuclear disaster prevention and also cooperate with international organizations. This annual report summarized the activities of JAEA/NEAT in the fiscal year 2008.

Journal Articles

A Personal use program for calculation of aviation route doses

Yasuda, Hiroshi*; Sato, Tatsuhiko; Terakado, Masato*

Proceedings of 12th International Congress of the International Radiation Protection Association (IRPA-12) (CD-ROM), 6 Pages, 2008/10

An Excel VBA program to calculate aviation route doses is developed for personal use by general public. This program named as "JISCARD EX" runs on a personal computer installed with the Microsoft Excel 2003/2007. Cosmic radiation dose rates at aviation altitude are calculated using the PARMA code developed in Japan. Calculated results are automatically summarized in another Excel worksheet as a report containing airport names, flying time, route dose and time plots of altitude, Rc and effective dose rate. This program will be open to the public from a web site of National Institute of Radiological Sciences.

Journal Articles

Trouble of a transformer with the no-voltage tap changer

Omori, Yoshikazu; Kurihara, Kenichi; Matsukawa, Makoto; Terakado, Tsunehisa; Furukawa, Hiroshi

Dai-17-Kai Bunshi Kagaku Kenkyusho Gijutsu Kenkyukai Hokokushu (CD-ROM), 4 Pages, 2006/03

no abstracts in English

JAEA Reports

Experimental Fast Reacter JOYO MK-III Functional Test; Secondary Cooling System Main Pumps Test

Terakado, Tsuguo; Morimoto, Makoto; Izawa, Osamu; Ishida, Koichi; Hoshino, Katsuaki; Suzuki, Shinya; Ito, Hideaki; Aoki, Hiroshi; Odo, Toshihiro

JNC TN9430 2004-003, 87 Pages, 2004/03

JNC-TN9430-2004-003.pdf:2.86MB

This paper describes the results of Secondary Cooling System main pumps test ,which were done as a part of JOYO MK-3 function test. The function tests were cexcuted to get the operating characteristics of secondary cooling system, after the Intermediate Heat Exchangers, Dump Heat Exchangers, secondary main pump motors, pump speed control board and rheostat were replaced in the MK-3 conversion. These tests are composed of six items. These tests purpose are confirmed in the function of the Main pumps, sodium purification system and argon cover gas pressure control system in Secondary Cooling System. (1) SKS-205-1: flow control test, (2) SKS-205-2: flow coast down characteristics test, (3) SKS-205-3: running operation test, (4) SKS-205-4: pump vibration measurement test, (5) SKS-212: secondary sodium purification system electromagnetic-pump flow control test, (6) SKS-213: argon cover gas pressure in secondary cooling system pressure control test function tests are satisfied the design criteria. We have confirmed the system performance of the main pump, secondary sodium purification system and argon cover gas pressure control system in the Secondary Cooling System after the MK-3 conversion.

JAEA Reports

Development of the Automatic Control Rod Operation System for JOYO; Appreciation of apply to MK-III reactor operation

Terakado, Tsuguo; Hoshino, Katsuaki; Suzuki, Shinya; Ito, Hideaki; Aoki, Hiroshi; Odo, Toshihiro

JNC TN9410 2004-008, 55 Pages, 2004/03

JNC-TN9410-2004-008.pdf:1.82MB

The automatic control rod operation system was developed to control the JOYO reactor power automatically in all operation modes(critical approach, cooling system heat up, power ascent and power descent), development began in 1989. Prior to applying, we are examined possibility of apply to the automatic control rod operation guide system which developed in MK-2 operation to get the control rod operation guide data in MK-3 performance tests. The main results are as follows: (1).Critical approach mode in control rod operation guide function will be need tuning of fuzzy algorisms structure for changed MK-3 reactor critical point. (2).Cooling system heet up mode, power ascent mode and power descent mode will be supply to good guidance at MK-3 reactor operation. Because, power change rate and cooling system heet up rate same MK-2 reactor operation. (3).Plant operation guide function will be need change, based on MK-3 reactor operation manual. (4).The automatic control rod operation guide system will be need renewal for system maintainability.

Journal Articles

A New intelligent coil current control system combined with a synchronous generator and a diode rectifier

Shimada, Katsuhiro; Omori, Yoshikazu; Furukawa, Hiroshi*; Terakado, Tsunehisa; Matsukawa, Makoto; Kurihara, Kenichi

Proceedings of International Conference on Electrical Engineering 2004 (ICEE 2004), p.777 - 781, 2004/00

We developed a new coil current control system for a power supply that consists of a synchronous generator and diode rectifiers. Test results are reported for the toroidal field coil power supply of JT-60, a world-class tokamak-type fusion device. This coil current control system has been designed to improve the control flexibility of the plasma discharge, and to introduce new functions. A state feedback control method is adopted to control coil current. Limit functions for the generator field current, the generator output voltage, and the toroidal field coil voltage have been added to the original coil current control system. Moreover, the abnormal state detection function of a coil is implemented for safety. The developed new intelligent control system has been tested and its performance was confirmed.

Journal Articles

Design and analysis of plasma position and shape control in superconducting tokamak JT-60SC

Matsukawa, Makoto; Ishida, Shinichi; Sakasai, Akira; Urata, Kazuhiro*; Senda, Ikuo*; Kurita, Genichi; Tamai, Hiroshi; Sakurai, Shinji; Miura, Yushi; Masaki, Kei; et al.

Fusion Engineering and Design, 66-68(1-4), p.703 - 708, 2003/09

 Times Cited Count:2 Percentile:19.02(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

MK-III Modification work of heat transport system in JOYO; Dismantling and sodium cleaning of secondary cooling system components

Ishii, Takayuki; Isozaki, Kazunori; Ashida, Takashi; Minakawa, Satoru; Terakado, Tsuguo; Nogami, Hiroshi*; Kakurai, Katsuhiko*; Ueda, Soji*; Kawahara, Hirotaka; Ichige, Satoshi; et al.

JNC TN9410 2002-013, 86 Pages, 2002/11

JNC-TN9410-2002-013.pdf:68.29MB

The MK-III project has been proceeding to improve the irradiation capability of the experimental fast reactor JOY0. The MK-III project has three major purposes such as increase high neutron flux, improvement of plant availability factor and upgrading in irradiation techniques. Thermal output by core transformation for high neutron flux was increased from 100MWt to 140MWt. The main components in the cooling system such as IHX(Intermediate Heat Exchanger) and DHX(Dump Heat Exchanger) were replaced in MK-III modification in order to increase heat removal capability. Heat transfer capacity of IHX was increased from 50MWt/Unit to 70MWt/Unit and that of DHX was increased from 25MWt/Unit to 35MWt/Unit. These components replacement has been safety completed from october 30, 2000 through September 21, 2001. This report summarizes the way, results and safety measures about dismantling of no sodium adhered components and such as DHX blower and sodium cleaning of sodium components such as the DHX, the pipes connected with DHX and secondary side of IHX. Dismantling and sodium cleaning of secondary cooling system components were performed safely and efficiently as almost planned. The total amount of removed sodium was about 13.5kg.

Journal Articles

Development and operational experiences of the JT-60U tokamak and power supplies

Hosogane, Nobuyuki; Ninomiya, Hiromasa; Matsukawa, Makoto; Ando, Toshiro; Neyatani, Yuzuru; Horiike, Hiroshi*; Sakurai, Shinji; Masaki, Kei; Yamamoto, Masahiro; Kodama, Kozo; et al.

Fusion Science and Technology (JT-60 Special Issue), 42(2-3), p.368 - 385, 2002/09

 Times Cited Count:2 Percentile:17.07(Nuclear Science & Technology)

This paper reviews developments of the JT-60U tokamak and coil power supplies and their operational experiences obtained to date. The JT-60U is a large tokamak upgraded from the original JT-60 to obtain high plasma current, large plasma volume and highly elongated divertor configurations. In the modification, all components inside the bore of toroidal magnetic field coils, a vacuum vessel, poloidal magnetic field coils (PF-coils), divertor etc., were renewed. Furthermore, boron carbide converted CFC tiles were used as divertor tiles to reduce erosion of carbon-base tiles. Later, a semi-closed divertor with pumps was installed in the replacement of the open divertor. Various technologies and ideas introduced to develop these components their operational experiences provide important data for designing future tokamaks. Also, major troubles that had influence on the JT-60U operations are described. As a maintenance issue for tokamaks using deuterium fueling gas, a method for reducing radiation exposure of in-vessel workers are introduced.

Journal Articles

First test results for the ITER central solenoid model coil

Kato, Takashi; Tsuji, Hiroshi; Ando, Toshinari; Takahashi, Yoshikazu; Nakajima, Hideo; Sugimoto, Makoto; Isono, Takaaki; Koizumi, Norikiyo; Kawano, Katsumi; Oshikiri, Masayuki*; et al.

Fusion Engineering and Design, 56-57, p.59 - 70, 2001/10

 Times Cited Count:17 Percentile:74.89(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Pulse operation test of the ITER central solenoid model coil using the JT-60 power supply

Terakado, Tsunehisa; Okano, Jun; Shimada, Katsuhiro; Miura, Yushi; Yamashita, Yoshiki*; Matsukawa, Makoto; Hosogane, Nobuyuki; Tsuji, Hiroshi; Ando, Toshinari*; Takahashi, Yoshikazu; et al.

JAERI-Tech 2001-056, 24 Pages, 2001/08

JAERI-Tech-2001-056.pdf:1.17MB

no abstracts in English

Journal Articles

CS model coil test facility

Kato, Takashi; Nakajima, Hideo; Isono, Takaaki; Hamada, Kazuya; Kawano, Katsumi; Sugimoto, Makoto; Nunoya, Yoshihiko; Koizumi, Norikiyo; Matsui, Kunihiro; Oshikiri, Masayuki*; et al.

Teion Kogaku, 36(6), p.315 - 323, 2001/06

no abstracts in English

Journal Articles

Progress of the ITER central solenoid model coil programme

Tsuji, Hiroshi; Okuno, Kiyoshi*; Thome, R.*; Salpietro, E.*; Egorov, S. A.*; Martovetsky, N.*; Ricci, M.*; Zanino, R.*; Zahn, G.*; Martinez, A.*; et al.

Nuclear Fusion, 41(5), p.645 - 651, 2001/05

 Times Cited Count:55 Percentile:83.06(Physics, Fluids & Plasmas)

no abstracts in English

Journal Articles

Fabrication of ITER central solenoid model coil-outer module

Ando, Toshinari; Hiyama, Tadao; Takahashi, Yoshikazu; Nakajima, Hideo; Kato, Takashi; Sugimoto, Makoto; Isono, Takaaki; Kawano, Katsumi; Koizumi, Norikiyo; Hamada, Kazuya; et al.

IEEE Transactions on Applied Superconductivity, 9(2), p.628 - 631, 1999/06

 Times Cited Count:8 Percentile:51.51(Engineering, Electrical & Electronic)

no abstracts in English

Journal Articles

Interaction between RF and edge plasma during ICRF heating in JT-60

Fujii, Tsuneyuki; Saigusa, Mikio; Kimura, Haruyuki; *; Tobita, Kenji; Nemoto, Masahiro; Kusama, Yoshinori; Seki, Masami; Moriyama, Shinichi; Nishitani, Takeo; et al.

Fusion Engineering and Design, 12, p.139 - 148, 1990/00

 Times Cited Count:25 Percentile:89.09(Nuclear Science & Technology)

no abstracts in English

Oral presentation

Operating experience with large flywheel motor-generators for JT-60 fusion device; The 20-year history and the troubles

Omori, Yoshikazu; Kurihara, Kenichi; Matsukawa, Makoto; Terakado, Tsunehisa; Okano, Jun; Furukawa, Hiroshi

no journal, , 

no abstracts in English

Oral presentation

Design study of the power supply system for JT-60SA

Shimada, Katsuhiro; Terakado, Tsunehisa; Omori, Yoshikazu; Okano, Jun; Furukawa, Hiroshi; Shibata, Kazuyuki; Terakado, Hiroyuki; Shibata, Takatoshi; Matsukawa, Makoto; Kurihara, Kenichi

no journal, , 

no abstracts in English

Oral presentation

A Personal use program for calculation of aviation route doses

Yasuda, Hiroshi*; Sato, Tatsuhiko; Terakado, Masato*

no journal, , 

An Excel VBA program to calculate aviation route doses is developed for personal use by general public. This program named as JISCARD EX runs on a personal computer installed with the Microsoft Excel 2003/2007. Cosmic radiation dose rates at aviation altitude are calculated using the PARMA code developed in Japan. Calculated results are automatically summarized in another Excel worksheet as a report containing airport names, flying time, route dose and time plots of altitude, Rc and effective dose rate. This program will be open to the public from a web site of National Institute of Radiological Sciences.

25 (Records 1-20 displayed on this page)