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Journal Articles

Current status and future prospects of the Horonobe International Project (HIP), 4; Task C: Full-scale Engineering Barrier System (EBS) dismantling experiment

Ono, Hirokazu

Genshiryoku Bakkuendo Kenkyu (CD-ROM), 31(2), p.140 - 143, 2024/12

In the geological disposal of high-level radioactive waste, after emplacement of an EBS, the near-field environment is affected by processes such as heat release from the waste, groundwater infiltration into the EBS, swelling and deformation of the buffer material, and chemical reactions between groundwater and minerals. It is crucial to develop simulation codes to evaluate such coupled thermal-hydraulic-stress-chemical (THMC) processes for safety assessment of geological disposal. The full-scale vertical-emplacement EBS experiment (Horonobe EBS experiment) has been undertaken in the 350 m gallery of the Horonobe Underground Research Laboratory (URL) with the Horonobe geological environment. In the Horonobe EBS experiment, various sensors were installed in the buffer and backfill material to obtain the data required to evaluate coupled THMC processes in near-field. In Task C of the Horonobe International Project (HIP), the dismantling experiment of the Horonobe EBS experiment will be carried out and the data obtained from this experiment will be used to understand the coupled processes and to evaluate the simulation code.

Journal Articles

Japan Atomic Energy Agency; Contribution to the decommissioning of the Fukushima Daiichi Nuclear Power Station and the reconstruction of Fukushima Prefecture at the Naraha center for Remote Control technology development

Morimoto, Kyoichi; Ono, Takahiro; Kakutani, Satomi; Yoshida, Moeka; Suzuki, Soichiro

Journal of Robotics and Mechatronics, 36(1), p.125 - 133, 2024/02

The Naraha Center for Remote Control Technology Development was established for the purpose of developing and verifying remote control equipment for promoting the decommissioning of the Fukushima Daiichi Nuclear Power Station and the external use of this center was started in 2016. The mission of this center is to contribute to the decommissioning of the Fukushima Daiichi Nuclear Power Station and for the reconstruction of Fukushima Prefecture. In this review, we describe the equipment related to the full-scale mock-up test, the component test for a remote-control device and the virtual reality system in this center. In addition, the case examples for usage of these equipment are introduced.

JAEA Reports

Plan of vibration tests for estimation of seismic performance of ITER tokamak

Takeda, Nobukazu; Nakahira, Masataka

JAERI-Tech 2004-073, 59 Pages, 2005/01

JAERI-Tech-2004-073.pdf:11.36MB

The ITER toamak is composed of major components such as superconducting magnet and vacuum vessel whose operation temperatures are changed from room temperature to 4 K and room temperature to 200$$^{circ}$$C, respectively. The gravity support of the tokamak is flexible in order to accept the thermal deformation caused by temperature change. This structural feature causes the complex behaviors of the tokamak during seismic events. Therefore, the mechanical characteristics of the flexible support have to be investigated in detail. The present report describes the global plan of the series of vibration tests to estimate the seismic performance of the ITER tokamak. Although it is ideal that the vibration tests are carried out using a full-scale model, scale models are planned due to the limitation of the test facilities. The test results can be estimated by a scaling law. When the scaling law cannot be applied to some performances, the test is performed using a full-scale model. In addition, the other tests such as vacuum vessel and small-scaled models of the support structure are also planned.

JAEA Reports

Performance test results of mock-up model test facility with a full-scale reaction tube for HTTR hydrogen production system (Contract research)

Inagaki, Yoshiyuki; Hayashi, Koji; Kato, Michio; Fujisaki, Katsuo; Aita, Hideki; Takeda, Tetsuaki; Nishihara, Tetsuo; Inaba, Yoshitomo; Ohashi, Hirofumi; Katanishi, Shoji; et al.

JAERI-Tech 2003-034, 129 Pages, 2003/05

JAERI-Tech-2003-034.pdf:7.62MB

no abstracts in English

JAEA Reports

Development of fabrication technology for ITER vacuum vessel

Nakahira, Masataka; Shibanuma, Kiyoshi; Kajiura, Soji*; Shibui, Masanao*; Koizumi, Koichi; Takeda, Nobukazu; Kakudate, Satoshi; Taguchi, Ko*; Oka, Kiyoshi; Obara, Kenjiro; et al.

JAERI-Tech 2002-029, 27 Pages, 2002/03

JAERI-Tech-2002-029.pdf:2.04MB

The ITER vacuum vessel (VV) R&D has progressed with the international collaborative efforts by the Japan, Russia and US Parties during the Engineering Design Activities (EDA). Fabrication and testing of a full-scale VV sector model and a port extension have yielded critical information on the fabrication and assembly technologies of the vacuum vessel, magnitude of welding distortions, dimensional accuracy and achievable tolerances during sector fabrication and field assembly. In particular, the dimensional tolerances of $$pm$$3 mm for VV sector fabrication and $$pm$$10 mm for VV sector field assembly have been achieved and satisfied the requirements of $$pm$$5 mm and $$pm$$20 mm, respectively. Also, the basic feasibility of the remote welding robot has been demonstrated. This report presents detailed fabrication and assembly technologies such as welding technology applicable to the thick wall without large distortion, field joint welding technology between sectors and remote welding technology through the VV R&D project.

Journal Articles

Fabrication and assembly of full-scale sector models for ITER vacuum vessel

Koizumi, Koichi; Nakahira, Masataka; Oka, Kiyoshi; ; Takahashi, Hiroyuki*; Tada, Eisuke; Ioki, Kimihiro*; Johnson, G.*; Onozuka, Masanori*; Y.Utin*; et al.

Fusion Technology, 34(3), p.586 - 590, 1998/11

no abstracts in English

Journal Articles

Fabrication of full-scale sector model for ITER vacuum vessel

Koizumi, Koichi; Nakahira, Masataka; ; Takahashi, Hiroyuki*; Tada, Eisuke; Ioki, Kimihiro*; Johnson, G.*; Onozuka, Masanori*; Y.Utin*; Sonnazzaro, G.*; et al.

Proceedings of 17th IEEE/NPSS Symposium Fusion Engineering (SOFE'97), 2, p.933 - 936, 1998/00

no abstracts in English

JAEA Reports

JAEA Reports

Full-Scale MarkII CRT Program Data Report No.12 (TEST 1205)

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JAERI-M 9405, 121 Pages, 1981/03

JAERI-M-9405.pdf:3.02MB

no abstracts in English

JAEA Reports

Full-scale MarkII CRT Program Data Report No.11 (TEST 1204)

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JAERI-M 9404, 121 Pages, 1981/03

JAERI-M-9404.pdf:2.99MB

no abstracts in English

JAEA Reports

Full-Scale Mark II CRT Program Data Report No.10 (TEST 1203)

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JAERI-M 9403, 122 Pages, 1981/03

JAERI-M-9403.pdf:2.78MB

no abstracts in English

JAEA Reports

Full-Scale Mark-II CRT Program Data Report,No.9; TEST1202

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JAERI-M 8961, 121 Pages, 1980/07

JAERI-M-8961.pdf:2.67MB

no abstracts in English

JAEA Reports

Full-Scale Mark-II CRT Program Data Report,No.8; TEST 1201

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JAERI-M 8887, 132 Pages, 1980/06

JAERI-M-8887.pdf:3.8MB

no abstracts in English

JAEA Reports

Full-Scale MKII Containment Response Test Facility Description

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JAERI-M 8780, 134 Pages, 1980/03

JAERI-M-8780.pdf:4.05MB

no abstracts in English

JAEA Reports

Full-Scale Mark-II CRT Program Data Report No.7; Test 3102

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JAERI-M 8765, 123 Pages, 1980/03

JAERI-M-8765.pdf:2.69MB

no abstracts in English

JAEA Reports

Full-Scale Mark-II CRT Program Data Report No.5; Test 2101

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JAERI-M 8764, 118 Pages, 1980/03

JAERI-M-8764.pdf:2.66MB

no abstracts in English

JAEA Reports

Full-Scale Mark-II CRT Program Data Report No.4; Test 1101

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JAERI-M 8763, 116 Pages, 1980/03

JAERI-M-8763.pdf:2.52MB

no abstracts in English

JAEA Reports

Full-Scale Mark-II CRT Program Data Report No.3; Test 0004

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JAERI-M 8762, 108 Pages, 1980/03

JAERI-M-8762.pdf:2.44MB

no abstracts in English

JAEA Reports

Full-Scale Mark-II CRT Program Data Report No.2; Test 0003

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JAERI-M 8761, 116 Pages, 1980/03

JAERI-M-8761.pdf:2.64MB

no abstracts in English

22 (Records 1-20 displayed on this page)