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JAEA Reports

Training programs of emergency response robots operation for operators in each site of JAEA beginner class / intermediate class

Chiba, Yusuke; Nishiyama, Yutaka; Tsubaki, Hirohiko; Iwai, Masaki

JAEA-Technology 2019-002, 29 Pages, 2019/03

JAEA-Technology-2019-002.pdf:2.43MB

Act on Special Measures Concerning Nuclear Emergency Preparedness was amended on the 30th of October in 2017. As the JAEA Emergency Assistance Organization, Maintenance and Operation Section for Remote Control Equipment in Naraha Center for Remote Control Technology Development started training for emergency response robots operation for operators in each site of JAEA in response to the new amendment. The training consists of three operations: small crawler-type mobile scouting robots, big crawler-type mobile robots with a manipulator or a long tong and small radio-controlled helicopters. The training has three classes (beginner, intermediate and advanced classes) depending on skills and experiences. This paper reports the training programs of emergency response robots operation of the beginner and intermediate classes which were used in the first half of fiscal 2018.

Journal Articles

Challenge to decommissioning of Fukushima Daiichi Nuclear Power Station by applying VR technology

Horiguchi, Kenichi

Gijutsushi, 30(4), p.8 - 11, 2018/04

The verification activity and training of operation in the Fukushima-Daiichi Nuclear Power Station are more important than another Nuclear Power Station. At the JAEA Naraha Remote Technology Development Center, it has being carried out the development work to apply to the decommissioning work by using the full sized mock up and VR system which is built based on location surveying data of inside the reactor building. It is able to contribute to the decommissioning more reliably and efficiently.

Journal Articles

Towards enhancement of test facilities for supporting nuclear decommissioning by remote technology

Kawabata, Kuniaki; Mori, Fumiaki*; Shirasaki, Norihito; Tanifuji, Yuta; Hanari, Toshihide

Proceedings of 2017 IEEE/SICE International Symposium on System Integration (SII 2017), p.450 - 455, 2018/02

This paper describes the test facilities and experimental environments for supporting the decommissioning of the nuclear facilities especially Fukushima Daiichi Nuclear Power Station by remote operation. Naraha Remote Technology Development Center of Japan Atomic Energy Agency is an institution for such purpose. Mock-up staircase, robot testing pool and motion capture arena are already installed and full service and support began from April, 2016. We are also designing and developing some experimental environment for remotely operated robots for nuclear decommissioning. In this paper, we describe current status and development of test facilities of Naraha Remote Technology Development Center, Japan Atomic Energy Agency.

Journal Articles

Development of technologies of cutting and decontamination employing high power fiber laser

Toyama, Shinichi; Minehara, Eisuke*

Dekomisshoningu Giho, (56), p.55 - 65, 2017/09

Development of the steel cutting technology which employs high power fiber laser for the industrial applicability of the laser technology has been carried out at The Wakasa Wan Energy Research Center (WERC). At present, the laser technologies for dismantling and decontamination are concurrently being developed to the application measure of nuclear dismantling for domestic nuclear power plants in the future. Dismantling of nuclear facilities is now under the development in the world. The necessity of the technology is increasing and the development is strongly expected. Beside the relative easiness to handle compared with other laser system, suppression of production of secondary radioactive waste and dose exposure can be realized by the dramatic improvement by excelled thermal density of fiber laser. This paper provides recent results from cutting technology for thick steels aiming disassembling nuclear pressure vessel, and decontamination machine technology which works under high radiation dose, explaining the results from cutting experiment of steels and the actual equipment and from the radiation resistance experiment for component devices.

Journal Articles

Field emission-type scanning electron microscope for examination of irradiated fuels

Yasuda, Ryo; Mita, Naoaki; Nishino, Yasuharu; Nakata, Masahito; Nozawa, Yukio; Harada, Katsuya; Kushida, Teruo; Amano, Hidetoshi

Nuclear Technology, 151(3), p.341 - 345, 2005/09

 Times Cited Count:0 Percentile:100(Nuclear Science & Technology)

The Field Emission type Scanning Electron Microscope (FE-SEM), which is one of effective tools for observation of micr-structures, was installed at the Reactor Fuel Examination Facility (RFEF) in JAERI. The FE-SEM is equipped in a large shield vessel with remote handling systems to keep safety of operators and is modified to enable to manipulate high radioactive materials. The Energy Dispersive Spectrometer (EDS) with radiation-shielded collimators has been also equipped on the FE-SEM to determine element compositions of the observed material samples. Characterization tests were carried out using deposited gold film and Zircaloy cladding tubes with hydrides to confirm the machine performance after the modifications. In the results of the tests, high-resolution images without some noises and fogs were obtained with high magnification above 10,000. Those results show that the FE-SEM keeps the high performance after some improvements and modifications for shielding $$gamma$$-rays and handling radioactive samples.

JAEA Reports

Development of remote controlled type field-emission type scanning electron microscope

Yasuda, Ryo; Nishino, Yasuharu; Mita, Naoaki; Nakata, Masahito; Harada, Katsuya; Nozawa, Yukio; Amano, Hidetoshi

JAERI-Tech 2002-081, 34 Pages, 2002/10

JAERI-Tech-2002-081.pdf:11.76MB

Information about the fuel behavior under high burn-up operation is needed to assess the safety of the high burn-up fuels. Microstructures in irradiated fuel pellets and Zircaloy tubes influence on their integrity. The fundamental information about microstructures is necessary to estimate the formation mechanism and change in the properties of the fuels.The Field Emission type Scanning Electron Microscope (FE-SEM) has been hence installed at the Reactor Fuel Examination Facility (RFEF). FE-SEM is designed for the remote handling type to use high radioactive materials and has equipments to keep safety for operators. Charctarization tests were carried out using Zircaloy cladding tubes with oxide films and hydrides to confirm machine performance. In the results of the tests, high-resolution images with a magnification of 30,000 were obtained. Those results show that the apparatus is maintained high performance as well as standard type.

JAEA Reports

Improvement and mock-up test of vinyl bag for critical experiment fueled with plutonium at STACY (Contract research)

Onodera, Seiji; Sugawara, Susumu; Kobayashi, Heigo; Haga, Koichi; Fukushima, Susumu*; Shichiji,Isamu*; Ono, Akio

JAERI-Tech 2002-070, 77 Pages, 2002/09

JAERI-Tech-2002-070.pdf:8.74MB

no abstracts in English

Journal Articles

Activities for drafting standards of nondestructive testing by infrared thermography

Ishii, Toshimitsu

Hihakai Kensa, 51(6), p.328 - 332, 2002/06

no abstracts in English

Journal Articles

Manufacturing and maintenance technologies developed for a thick-wall structure of the ITER vacuum vessel

Onozuka, Masanori*; Alfile, J. P.*; Aubert, P.*; Dagenais, J.-F.*; Grebennikov, D.*; Ioki, Kimihiro*; Jones, L.*; Koizumi, Koichi; Krylov, V.*; Maslakowski, J.*; et al.

Fusion Engineering and Design, 55(4), p.397 - 410, 2001/09

 Times Cited Count:18 Percentile:19.83

Development of welding, cutting and non-destructive testing (NDT) techniques, and development of remotized systems, have been conducted for on-site manufacturing and maintenance of the thick wall structure of the ITER vacuum vessel (VV). Conventional techniques, including TIG (tungsten inert gas) welding, plasma cutting and ultrasonic inspection, have been improved and optimized for the application to thick austenitic stainless steel plates. In addition, advanced methods have been investigated including reduced-pressure electron-beam and multi-pass NdYAG (neodymium-doped yttrium aluminum garnet) laser welding, NdYAG laser cutting, and EMAT (electro-magnetic acoustic transducer) inspection to improve cost and technical performance. Two types of remotized systems with different payloads have been investigated and one of them has been fabricated and demonstrated in field joint welding, cutting, and NDT tests on test mockups and full-scale ITER VV sector models. The progress and results of this development to date provide a high level of confidence that the manufacturing and maintenance of the ITER VV is feasible.

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

Journal Articles

Development of a diagnostic technique using ultrasonic wave for evaluation of irradiation embrittlement in reactor pressure vessel materials

Ishii, Toshimitsu; Ooka, Norikazu; Hoshiya, Taiji; Kobayashi, Hideo*

KURRI-KR-62, p.29 - 41, 2001/03

no abstracts in English

JAEA Reports

PIE technology on mechanical tests for HTTR core component and structural materials developed at research hot laboratory

Kizaki, Minoru; Honda, Junichi; Usami, Koji; Ouchi, Asao*; Oeda, Etsuro; Matsumoto, Seiichiro

JAERI-Tech 2000-087, 50 Pages, 2001/02

JAERI-Tech-2000-087.pdf:2.78MB

no abstracts in English

Journal Articles

Development of a small specimen test machine to evaluate irradiation embrittlement of fusion reactor materials

Ishii, Toshimitsu; Omi, Masao; Saito, Junichi; Hoshiya, Taiji; Ooka, Norikazu; Jitsukawa, Shiro; Eto, Motokuni

Journal of Nuclear Materials, 283-287(Part.2), p.1023 - 1027, 2000/12

 Times Cited Count:7 Percentile:49.31

no abstracts in English

JAEA Reports

Development of JOYO plant operation management expert Tool (JOYPET)

; Terano, Toshihiro; ; ;

JNC-TN9410 2000-004, 30 Pages, 2000/03

JNC-TN9410-2000-004.pdf:0.86MB

The Operation and Maintenance Support Systems for JOYO are being developed, with the aim of ensuring the stable and safe operation of JOYO and improving operational reliability of future FBR plants. Plant Operation Management Expert Tool named JOYPET had been developed as one of the Operation and Maintenance Support Systems, which helps plant operation management. The following functions were developed and applied. (1)Papers management (Plant status management) function for maintenance activities (2)Isolation management support function for plant operation (3)Automatically drawing function of plant operation schedule (4)Isolation judgment function for plant operation By use this system, the plant management of JOYO was able to improved reliability and reduced manpower.

JAEA Reports

Development of resistance welding process; Manufacture of test specimens for ODS steel strength evaluation

; ; ; *; *

JNC-TN8410 2000-007, 89 Pages, 2000/03

JNC-TN8410-2000-007.pdf:6.28MB

(1)Outline of examination. Various test specimens were made to evaluate and confirm the weld strength properties of the oxide dispersion strengthened (ODS) cladding tube material (martensitic and ferritic steel), which had been manufactured in JFY 1997. The examination consisted of tensile tests (RT,650$$^{circ}$$C, 700$$^{circ}$$C, 800$$^{circ}$$C), internal pressure creep tests, internal pressure burst tests, and a rapid heating burst tests. (2)Examination results. The results of the tensile tests are as follows: (ferritic and martensitic) (a)All test specimens from RT to 700$$^{circ}$$C failed in the tube. The weld zones had not failed. (b)The test specimens at 800$$^{circ}$$C failed in the weld zones. There was little elongation. (ferritic) (a)The weld zone had fine grain structure and carbide precipitates. (martensitic) (a)Carbide had precipitated in the weld zone. From these results, the strength of weld zone decreased extremely at temperatures exceeding the endurance limit (700$$^{circ}$$C) All of the internal pressure burst test specimens and the rapid heating burst test specimens failed in the tube and not the weld zone. (3)The quality assurance method of the test specimens. The weld reliability of the test specimens were confirmed by the process control of the welding conditions, by using control test specimens, and ultrasonic testing. Confirmation of the process control of the welding conditions; current wave, the voltage waveform, the accelerogram, and the displacement ripple in the welding process was recorded to assure an abnormal value had not occurred. (Process control of welding condition) The results the current waveform, voltage waveform, accelerogram, and the displacement waveform were excellent. (test specimens) The weld joint was excellent based on metallography examination. (Ultrasonic testing) The length of the weld joint was measured and found to be adequate. The reliability the weld joint can be assured by using the above-mentioned method.

JAEA Reports

Improvement of DYANA ; The dynamic analysis program for event transition

*; *

JNC-TJ9440 2000-004, 22 Pages, 2000/03

JNC-TJ9440-2000-004.pdf:2.35MB

In the probabilistic safety assessment(PSA), the fault tree/event tree technique has been widely used to evaluate accident sequence frequencies. However, event tansition which operators actually face can not be dynamically treated by the conventional technique. Therefore, we have made the dynamic analysis program(DYANA) for event transition for a liquid metal cooled fast breeder reactor. In the previous development, we made basic model for analysis. However, we have a probrem that calculation time is too long. At the current term, we made parallelization of DYANA usig MPI. So we got good performance on WS claster. It performance is close to ideal one.

JAEA Reports

Development of welding technique by remote control at the JMTR hot laboratory

Shimizu, Michio; Iwamatsu, Shigemi; Takada, Fumiki; Sozawa, Shizuo; Kawamata, Kazuo; Oshima, Kunio; Tsuchiya, Kunihiko; Yamaura, Takayuki; Matsui, Yoshinori; Iwai, Takashi; et al.

JAERI-Tech 2000-029, p.48 - 0, 2000/03

JAERI-Tech-2000-029.pdf:9.26MB

no abstracts in English

JAEA Reports

None

*

JNC-TJ1440 99-004, 62 Pages, 1999/06

JNC-TJ1440-99-004.pdf:4.47MB

no abstracts in English

JAEA Reports

None

JNC-TJ1400 99-003, 70 Pages, 1999/03

JNC-TJ1400-99-003.pdf:2.26MB

no abstracts in English

Journal Articles

Ultra-high radiation-resistant polymer materials

Morita, Yosuke; Udagawa, Akira

Genshiryoku eye, 44(5), p.40 - 45, 1998/05

no abstracts in English

94 (Records 1-20 displayed on this page)