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Journal Articles

2016 Professional Engineer (PE) test preparation course "Nuclear and Radiation Technical Disciplines"

Takahashi, Naoki; Yoshinaka, Kazuyuki; Harada, Akio; Yamanaka, Atsushi; Ueno, Takashi; Kurihara, Ryoichi; Suzuki, Soju; Takamatsu, Misao; Maeda, Shigetaka; Iseki, Atsushi; et al.

Nihon Genshiryoku Gakkai Homu Peji (Internet), 64 Pages, 2016/00

no abstracts in English

JAEA Reports

Construction of a car-borne survey system for measurement of dose rates in air; KURAMA-II, and its application

Tsuda, Shuichi; Yoshida, Tadayoshi; Nakahara, Yukio; Sato, Tetsuro; Seki, Akiyuki; Matsuda, Norihiro; Ando, Masaki; Takemiya, Hiroshi; Tanigaki, Minoru*; Takamiya, Koichi*; et al.

JAEA-Technology 2013-037, 54 Pages, 2013/10

JAEA-Technology-2013-037.pdf:4.94MB

JAEA has been performing dose rate mapping in air using a car-borne survey system KURAMA-II. The KURAMA system is a GPS-aided mobile radiation monitoring system that has been newly developed by Kyoto University Research Reactor Institute in response to the nuclear disaster. The KURAMA system is composed of an energy-compensated scintillation survey meter for measuring dose rate, electric device for controlling both the dose rates and the position data from a GPS module, a computer server for processing and analyzing data from KURAMA, and client PCs for providing for end users. The KURAMA-II has been improved in small-packaging, durability, and automated data transmission. In consequence, dose rate mapping in wide area has become possible in shorter period of time. This report describes the construction of KURAMA-II, its application and a suggestion of how to manage a large number of KURAMA-II.

JAEA Reports

Removal of the liquid waste storage tank LV-2 in JRTF, 1; Preparatory works

Satomi, Shinichi; Kanayama, Fumihiko; Hagiya, Kazuaki; Myodo, Masato; Kobayashi, Tadayoshi; Tomii, Hiroyuki; Tachibana, Mitsuo

JAEA-Technology 2008-067, 53 Pages, 2008/10

JAEA-Technology-2008-067.pdf:8.66MB

Dismantling activities of equipments in JAERI's Reprocessing Test Facility (JRTF) started from 1996 as a part of decommissioning of this facility. The large liquid waste storage tank LV-2 is scheduled to remove out as a whole tank without cutting in pieces from the annex building B to confirm safety and efficiency of this method from 2006. Before removal of the LV-2 tank, some preparatory works were carried out such as opening of concrete wall (LV-2 room) for the entrance of workers and materials, removal of pipes connected to the LV-2 tank, and decontamination of radioactive sludge in the LV-2 tank. Useful data were collected on manpower, radiation control and waste amount through the preparatory works, and work efficiency was analyzed by use of these data. It was compared manpower between core boring and hand-breaker crushing activities in the concrete wall opening work. It was also confirmed that local exposure of worker could be reduced in large extent by an addition of vinyl chloride cover on worker's ventilated suit.

JAEA Reports

Removal of penetrating pipes by dry wire-saw technology

Myodo, Masato; Kobayashi, Tadayoshi; Tomii, Hiroyuki

JAEA-Technology 2008-001, 46 Pages, 2008/03

JAEA-Technology-2008-001.pdf:19.05MB

Dry wire-saw technology was applied for removal of penetrating pipes in annex building B of JAEA's reprocessing test facility (JRTF) and concrete blocks with penetrating pipes were successfully removed. The concrete block was cracked by a silent demolition agent and was easily separated into concrete and pipes by the secondary crushing by use of a hand-breaker. Effectiveness of the dry wire-saw technology for removal of penetrating pipes was discussed and evaluated based on various work data obtained in the present activity. The use of silent demolition agent was found to be very effective for the secondary crushing of concrete blocks and its charging condition into concrete was established so as to give effective cracks for the secondary crushing. As a result of this activity, it was confirmed that the dry wire-saw technology coupled with use of a silent demolition agent was one of hopeful candidates to remove penetrating pipes safely and effectively in reprocessing facilities.

Journal Articles

Ratio of transverse diffusion coefficient to mobility of electrons in high-pressure xenon and xenon doped with hydrogen

Kobayashi, Shingo*; Hasebe, Nobuyuki*; Hosojima, Takehiro*; Ishizaki, Takeshi*; Iwamatsu, Kazuhiro*; Mimura, Mitsuteru*; Miyachi, Takashi*; Miyajima, Mitsuhiro*; Pushkin, K.*; Tezuka, Chikara*; et al.

Japanese Journal of Applied Physics, Part 1, 45(10A), p.7894 - 7900, 2006/10

 Times Cited Count:13 Percentile:44.97(Physics, Applied)

We have obtained the ratio of transverse diffusion coeffcient to mobility of electrons multiplied by the elementary charge, in Xe and Xe+H$$_{2}$$ under electric fields at a higher pressure of 1 MPa in comparison with preceding experiments. The result shows that the density effect (non-linear effect) of the ratio in both of pure Xe and Xe+H$$_{2}$$ is $$<$$15% below 1 MPa over the reduced electric field range from 0.08 to 0.6$$times$$10$$^{-17}$$V$$cdot$$cm$$^{2}$$. We also found that the diffusion of an electron swarm is suppressed by adding trace of hydrogen to high-pressure xenon gas. Discussion is made of Xe+H$$_{2}$$ gas to a new $$gamma$$-ray camera. Trace of hydrogen to high-pressure xenon gas. Discussion is made of Xe+H$$_{2}$$ gas to a new $$gamma$$-ray camera.

Journal Articles

Results and experiences of the decommissioning of JAERI's Reprocessing Test Facility

Kobayashi, Tadayoshi

Dai-17-Kai Genshiryoku Shisetsu Dekomisshoningu Gijutsu Koza Tekisuto, p.103 - 124, 2006/02

no abstracts in English

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

JAEA Reports

Report on long range alpha detector (LRAD) performance tests

Kobayashi, Hirohide; ; ; ; Ebana, Minoru*

JNC TN8410 2002-011, 24 Pages, 2002/10

JNC-TN8410-2002-011.pdf:4.36MB

At present, alpha contamination measurement on objects is conducted with ZnS scintillation survey meter (direct method) and smear test (indirect method). But it is difficult to measure large and complicated objects by direct method. Long Range Alpha Detector (LRAD) was produced as a solution for this problem. We carried out performance tests of this LRAD. As a result of the performance tests, we confirmed the linear relation between the measurement values of LRAD and alpha-radioactivity on the surface of objects.

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:4 Percentile:25.56(Robotics)

no abstracts in English

JAEA Reports

Characteristics and maintenance requirements for the sampling pump of the stationary gaseous effluent monitor

Kobayashi, Hirohide; ; ; Maruo, Yoshihiro; Miyabe, Kenjiro; *

JNC TN8410 2002-006, 82 Pages, 2002/08

JNC-TN8410-2002-006.pdf:2.58MB

The stationary gaseous effluent monitor is equipment intended for continuously monitoring radioactivity in gaseous effluents released from the nuclear facilities. This monitor consists of sampling, detection and control assemblies. The sampling pump is a most integral part of the sampling assembly and required to be operated with an appropriate pressure to keep the continuous monitoring. However, in 1998, the failures of sampling pumps had successively occurred.This was due to the overload in pressure at the intake or the outlet. To prevent from the failures of sampling pumps, the overload characteristics and the mean time between failures (MTBF) were investigated. The following results were obtained. (1)The performance and tolerance tests with rapid increase of air pressure were carried out. The sampling pumps could withstand two or three times higher pressure than the regularly operating pressure during a few minutes. But, after that, the pump suddenly fell down by an over-current relay (OCR). (2)The MTBF were analyzed on the basis of the maintenance and repair records over a period from 1988 to 1998. The MTBF of a sampling pump were in the range from 7,600 to 35,500 hours. For a preventive maintenance, the consumption parts, such as a carbon blade and a bearing of rotor shaft, etc., should be replaced periodically.

Journal Articles

Development of remote surveillance squads for nuclear facility accidents

Kobayashi, Tadayoshi; Miyajima, Kazutoshi; Yanagihara, Satoshi

Keisoku Jido Seigyo Gakkai Dai-3-Kai Shisutemu Integureshon Bumon Koenkai (SI2002) Koen Rombunshu, 2, p.105 - 106, 2002/00

no abstracts in English

Journal Articles

Development of robots for nuclear accident in Japan Atomic Energy Reserch Institute, 1; Development of remote surveillance squad

Kobayashi, Tadayoshi; Miyajima, Kazutoshi; Yanagihara, Satoshi

Nihon Robotto Gakkai-Shi, 19(6), p.706 - 709, 2001/09

no abstracts in English

Journal Articles

Development of remote surveillance squad

Kobayashi, Tadayoshi; Miyajima, Kazutoshi; Yanagihara, Satoshi

Gekkan Shobo, 23(6), p.22 - 26, 2001/06

no abstracts in English

JAEA Reports

Experiments for the Assessment on Source Geometry of PWR Spent Fuel Assembly

; *; ; ; ; ; ; ; ; ; et al.

JAERI-M 82-202, 50 Pages, 1982/12

JAERI-M-82-202.pdf:1.43MB

no abstracts in English

JAEA Reports

Shielding Experiment of a Spent Fuel Transport Cask for a PWR Spent Fuel Assembly

; *; ; ; ; ; ; ; ; ; et al.

JAERI-M 82-201, 60 Pages, 1982/12

JAERI-M-82-201.pdf:1.99MB

no abstracts in English

Oral presentation

Production of plastic scintillation survey meter for clearance verification measurement

Tachibana, Mitsuo; Myodo, Masato; Shiraishi, Kunio; Kanayama, Fumihiko; Kobayashi, Tadayoshi; Ishigami, Tsutomu; Tomii, Hiroyuki

no journal, , 

no abstracts in English

18 (Records 1-18 displayed on this page)
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