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JAEA Reports

Annual report of Nuclear Emergency Assistance and Training Center; April 1, 2013 - March 31, 2014

Sato, Takeshi; Muto, Shigeo; Akiyama, Kiyomitsu; Aoki, Kazufumi; Okamoto, Akiko; Kawakami, Takeshi; Kume, Nobuhide; Nakanishi, Chika; Koie, Masahiro; Kawamata, Hiroyuki; et al.

JAEA-Review 2014-048, 69 Pages, 2015/02

JAEA-Review-2014-048.pdf:13.91MB

JAEA was assigned as a designated public institution under the Disaster Countermeasures Basic Act and under the Armed Attack Situations Response Act. Based on these Acts, the JAEA has the responsibility of providing technical support to the national government and/or local governments in case of disaster responses or response in the event of a military attack, etc. In order to fulfill the tasks, the JAEA has established the Emergency Action Plan and the Civil Protection Action Plan. In case of a nuclear emergency, NEAT dispatches specialists of JAEA, supplies the national government and local governments with emergency equipment and materials, and gives technical advice and information. In normal time, NEAT provides various exercises and training courses concerning nuclear disaster prevention to those personnel taking an active part in emergency response institutions of the national and local governments, police, fire fighters, self-defense forces, etc. in addition to the JAEA itself. The NEAT also researches nuclear disaster preparedness and response, and cooperates with international organizations. In the FY2013, the NEAT accomplished the following tasks: (1) Technical support activities as a designated public institution in cooperation with the national and local governments, etc. (2) Human resource development, exercise and training of nuclear emergency response personnel for the national and local governments, etc. (3) Researches on nuclear disaster preparedness and response, and sending useful information (4) International contributions to Asian countries on nuclear disaster preparedness and response in collaboration with the international organizations

Journal Articles

Correlation between cleavage fracture toughness and charpy impact properties in the transition temperature range of reactor pressure vessel steels

Onizawa, Kunio; Suzuki, Masahide

JSME International Journal, Series A, 47(3), p.479 - 485, 2004/07

In the structural integrity assessment of reactor pressure vessel, fracture toughness values are estimated by assuming that the radiation effect on fracture toughness is equivalent to that on Charpy properties. Therefore, it is necessary to establish the correlation between both properties especially on irradiation embrittlement. In this paper, we present the fracture toughness data obtained by applying the master curve approach that was adopted recently in the ASTM test method. Materials used in this study are five ASTM A533B class 1 steels and one weld metal. Neutron irradiation for Charpy-size specimens as well as standard Charpy-v specimens was carried out at the Japan Materials Testing Reactor. The shifts of the reference temperature on fracture toughness due to neutron irradiation are evaluated. Correlation between the fracture toughness reference temperature and Charpy transition temperature is established. Based on the correlation, the optimum test temperature for fracture toughness testing and the method to determine a lower bound fracture toughness curve are discussed.

Journal Articles

Development of remote surveillance squads for nuclear emergency

Yanagihara, Satoshi; Kobayashi, Tadayoshi; Miyajima, Kazutoshi; Tanaka, Mitsugu

International Journal of Robotics and Automation, 18(4), p.160 - 165, 2003/12

no abstracts in English

Journal Articles

Development of remote surveillance squads for nuclear facility accidents

Kobayashi, Tadayoshi; Miyajima, Kazutoshi; Yanagihara, Satoshi

Advanced Robotics, 16(6), p.497 - 500, 2002/09

 Times Cited Count:2 Percentile:79.98(Robotics)

no abstracts in English

Journal Articles

Results and analysis of the ASTM round robin on reconstitution

Onizawa, Kunio; Van Walle, E.*; Pavirich, W.*; Nanstad, R.*

NUREG/CR-6777, 81 Pages, 2002/08

no abstracts in English

Journal Articles

Correlation between cleavage fracture toughness and charpy impact properties in the transition range of reactor pressure vessel steels

Onizawa, Kunio; Suzuki, Masahide

Proceedings of Asian Pacific Conference on Fracture and Strength '01(APCFS '01) and International Conference on Advanced Technology in Experimental Mechanics '01 (ATEM '01), p.140 - 145, 2001/00

In the structural integrity assessment of reactor pressure vessel, fracture toughness values are estimated by assuming that the radiation effect on fracture toughness is equivalent to that on Charpy properties. Therefore, it is necessary to establish the correlation between both properties especially on irradiation embrittlement. In this paper, we present the fracture toughness data obtained by applying the master curve approach that was adopted recently in the ASTM test method. Materials used in this study are five ASTM A533B class 1 steels and one weld metal. Neutron irradiation for Charpy-size specimens as well as standard Charpy-v specimens was carried out at the Japan Materials Testing Reactor. The shifts of the reference temperature on fracture toughness due to neutron irradiation are evaluated. Correlation between the fracture toughness reference temperature and Charpy transition temperature is established. Based on the correlation, the optimum test temperature for fracture toughness testing and the method to determine a lower bound fracture toughness curve are discussed.

Journal Articles

Fracture toughness evaluation on neutron irradiation embrittlement for reactor pressure vessel steels

Onizawa, Kunio; Suzuki, Masahide

Proceedings of the 8th Japanese-German Joint Seminar on Structural Integrity and NDE in Power Engineering, p.62 - 69, 2001/00

To assure the structural integrity of reactor pressure vessel (RPV) throughout its operational life, fracture toughness of the steel after neutron irradiation must be determined. In this report the investigation on the master curve approach using Charpy-size specimens is presented for the precise evaluation of fracture toughness on irradiation embrittlement. Using some Japanese A533B-1 steels, fracture toughness tests in the transition range were performed varying specimen thickness. Charpy-size specimens were also irradiated at Japan Materials Testing Reactor. Applying the master curve method and JEAC method as well, the specimen size effect, temperature dependence and the lower bound were evaluated. The shifts of reference temperature of fracture toughness and Charpy transition temperature due to neutron irradiation were also compared and found to be almost equivalent.

JAEA Reports

JAEA Reports

Development of compact surveillance and monitoring system, COSMOS

Ogawa, Hironobu; Mukaiyama, Takehiko

JAERI-Tech 99-035, 106 Pages, 1999/03

JAERI-Tech-99-035.pdf:5.11MB

no abstracts in English

JAEA Reports

Auto-identification fiberoptical seal verifier

Yamamoto, Yoichi; Mukaiyama, Takehiko

JAERI-Tech 98-035, 31 Pages, 1998/08

JAERI-Tech-98-035.pdf:2.48MB

no abstracts in English

JAEA Reports

Development of integrated containment and surveillance system for fast critical facility FCA; Portal and penetration monitors

Mukaiyama, Takehiko; Ogawa, Hironobu; *

JAERI-Research 98-001, 76 Pages, 1998/01

JAERI-Research-98-001.pdf:2.97MB

no abstracts in English

Journal Articles

Critical analysis of results from the ASTM round-robin on reconstitution

Onizawa, Kunio; E.van-Walle*; R.K.Nanstad*; M.Sokolov*; W.Pavinich*

Small Specimen Test Techniques (ASTM STP 1329), 0, p.383 - 410, 1998/00

no abstracts in English

Journal Articles

Reconstitution of charpy impact specimens by surface activated joining

Nishiyama, Yutaka; Fukaya, Kiyoshi; Onizawa, Kunio; Suzuki, Masahide; *; *; *; *

Small Specimen Test Techniques (ASTM STP 1329), 0, p.484 - 494, 1998/00

no abstracts in English

Journal Articles

Correlation among the Changes in Mechanical properties due to neutron irradiation for pressure vessel steels

Onizawa, Kunio; Suzuki, Masahide

ISIJ International, 37(8), p.821 - 828, 1997/08

 Times Cited Count:2 Percentile:69.01(Metallurgy & Metallurgical Engineering)

no abstracts in English

Journal Articles

Report on the 37th INMM Annual Meeting

Yamamoto, Yoichi

Kaku Busshitsu Kanri Senta Nyusu, 26(2), p.5 - 7, 1997/02

no abstracts in English

Journal Articles

Auto COBRA seal verifier

Yamamoto, Yoichi; Mukaiyama, Takehiko; *; *

Proc. of Institute of Nucl. Materials Management (CD-ROM), 6 Pages, 1997/00

no abstracts in English

Journal Articles

Reliability test of CASDAC system, II

Yamamoto, Yoichi;

Dai-15-Kai Kaku Busshitsu Kanri Gakkai Nihon Shibu Nenji Taikai Rombunshu, 0, p.176 - 182, 1994/10

no abstracts in English

Journal Articles

Development of reconstitution technique of charpy impact specimens by surface-activated joining for reactor pressure vessel surveillance

Onizawa, Kunio; Fukaya, Kiyoshi; Nishiyama, Yutaka; Suzuki, Masahide; *; *

IWG-LMNPP-94/9, 0, 12 Pages, 1994/00

no abstracts in English

JAEA Reports

The Compact surveillance and monitoring system COSMOS; The Function and its operation

Ogawa, Hironobu; *

JAERI-M 93-217, 53 Pages, 1993/11

JAERI-M-93-217.pdf:1.12MB

no abstracts in English

JAEA Reports

CASDAC system, on-site multiplexer; User's guide

Yamamoto, Yoichi;

JAERI-M 93-055, 43 Pages, 1993/03

JAERI-M-93-055.pdf:0.85MB

no abstracts in English

30 (Records 1-20 displayed on this page)