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Journal Articles

Excavation cycle times recorded during sinking of a deep shaft in crystalline rock; A Case example at ventilation shaft of Mizunami URL, Japan

Sanada, Hiroyuki; Sato, Toshinori; Horiuchi, Yasuharu*; Mikake, Shinichiro; Okihara, Mitsunobu*; Yahagi, Ryoji*; Kobayashi, Shinji*

Tunnelling and Underground Space Technology, 50, p.68 - 78, 2015/08

 Times Cited Count:3 Percentile:77.84(Construction & Building Technology)

The Japan Atomic Energy Agency (JAEA) is implementing the Mizunami Underground Research Laboratory (MIU) Project to establish the scientific and technological basis for the geological disposal of High-level Radioactive Waste (HLW) in crystalline rocks. Excavation cycle times were recorded during the Ventilation Shaft sinking and compared with the planned excavation cycle times for evaluation of the baseline design plan. This included review of the cycle times in the design process and comparison with the actual construction results. The recorded results indicate that actual cycle times were twice as long as the design plan. This paper describes discussions on differences in cycle times between the design and actual times.

JAEA Reports

Study on engineering technologies in the Mizunami Underground Research Laboratory (FY 2013); Development of design and construction planning and countermeasure technologies (Contract research)

Kobayashi, Shinji*; Niimi, Katsuyuki*; Okihara, Mitsunobu*; Tsuji, Masakuni*; Yamada, Toshiko*; Sato, Toshinori; Mikake, Shinichiro; Horiuchi, Yasuharu*; Aoyagi, Yoshiaki

JAEA-Technology 2014-035, 172 Pages, 2015/01

JAEA-Technology-2014-035.pdf:91.27MB

The researches on engineering technology in the Mizunami Underground Research Laboratory (MIU) plan consists of (1) development of design and construction planning technologies, (2) development of construction technology, (3) development of countermeasure technology, (4) development of technology for security, and (5) development of technologies regarding restoration or reversal and mitigating of the excavation effect. To develop design and construction planning technologies, and countermeasure technology, the analysis of measured data during earthquake and seismic movement characteristics at deep underground, and the examination of grouting method were carried out. The knowledge of the seismic movements at deep underground was obtained by which observation records of seismometers at Mizunami underground research laboratory were analyzed to verify the earthquake-resistant design of the shafts and tunnels. As for" Study on grouting method at deep underground", Existing post-grouting methods for crystalline rock were reviewed, the applicability of pre-grouting technology was evaluated and study on experiment plan in MIU was carried out following the previous year.

Journal Articles

Analysis of excavation cycle time during sinking of the ventilation shaft at the Mizunami Underground Research Laboratory

Sanada, Hiroyuki; Sato, Toshinori; Horiuchi, Yasuharu*; Mikake, Shinichiro; Okihara, Mitsunobu*; Yahagi, Ryoji*; Kobayashi, Shinji*

Proceedings of 8th Asian Rock Mechanics Symposium (ARMS-8) (USB Flash Drive), 7 Pages, 2014/10

The Japan Atomic Energy Agency (JAEA) is implementing the Mizunami Underground Research Laboratory (MIU) Project to establish the scientific and technological basis for the geological disposal of High-level Radioactive Waste (HLW) in crystalline rocks. Excavation cycle times were recorded during the Ventilation Shaft sinking and compared with the planned excavation cycle times for evaluation of the baseline design plan. This included review of the cycle times in the design process and comparison with the actual construction results. The recorded results indicate that actual cycle times were twice as long as the design plan. This paper describes discussions on differences in cycle times between the design and result.

JAEA Reports

Study on engineering technologies in the Mizunami Underground Research Laboratory; FY2012 (Contract research)

Fukaya, Masaaki*; Noda, Masaru*; Hata, Koji*; Takeda, Yoshinori*; Akiyoshi, Kenji*; Ishizeki, Yoshikazu*; Kaneda, Tsutomu*; Sato, Shin*; Shibata, Chihoko*; Ueda, Tadashi*; et al.

JAEA-Technology 2014-019, 495 Pages, 2014/08

JAEA-Technology-2014-019.pdf:82.23MB

The researches on engineering technology in the Mizunami Underground Research Laboratory (MIU) plan consists of (1) research on engineering technology deep underground, and (2) research on engineering technology as a basis of geological disposal. The former research is mainly aimed in this study, which is categorized in (a) development of design and construction planning technologies, (b) development of construction technologies, (c) development of countermeasure technologies, and (d) development of technologies for security. In this study, the researches on engineering technology are being conducted in these four categories by using data measured during construction as a part of the second phase of the MIU plan.

JAEA Reports

Report on decontamination pilot projects to establish guidelines for environmental remediation of residential areas contaminated with radioactive materials discharged from the Fukushima Daiichi Nuclear Power Station Accident

Kihara, Shinji; Amazawa, Hiroya; Sakai, Akihiro; Nakata, Hisakazu; Kugo, Teruhiko; Matsuda, Norihiro; Oizumi, Akito; Sasamoto, Hiroshi; Mitsui, Seiichiro; Miyahara, Kaname

JAEA-Research 2013-033, 320 Pages, 2014/07

JAEA-Research-2013-033.pdf:119.17MB

JAEA performed decontamination experiments at two test sites that combined a range of buildings and different types of land use, located in Date and Minami Soma municipalities as field pilot projects in order to accumulate knowledge and data for full-scale decontamination activities performed by local governments. In the pilot projects, we established its plan using practical decontamination methods that can be easily implemented, according to decontamination targets (e.g., forests, agricultural land, residential house and roads) at each site. As a result of the decontamination, the average air dose rates were reduced to approximately one half of the values before decontamination.

JAEA Reports

Investigation on premise conditions for conceptual design of disposal facilities of radioactive wastes from viewpoint of safety assessment for near surface disposal of low-level radioactive wastes generated from research, industrial and medical facilities

Amazawa, Hiroya; Sakai, Akihiro; Sakamoto, Yoshiaki; Nakata, Hisakazu; Yamamoto, Masayuki*; Kawata, Yosuke*; Kihara, Shinji

JAEA-Technology 2010-043, 153 Pages, 2011/01

JAEA-Technology-2010-043.pdf:9.72MB

The Low-Level Radioactive Waste Disposal Project Center of Japan Atomic Energy Agency will establish a sitting criterion and procedure in a fair and transparent manner to settle on a near surface disposal facility for low level radioactive wastes generated from research, industrial and medical facilities, based on "Plan Concerning the Disposal Business Execution". Therefore, reasonable conceptual design of the disposal facilities will be planned under premise conditions of sitting condition on natural and social environment, waste form condition including radioactive inventory and waste packages, and technical standards based on "Law for the Regulations of Nuclear Source Material, Nuclear Fuel Material and Reactors" and "Law concerning Prevention of Radiation Hazards due to Radioisotopes, etc." and so on. This report summarizes the results of the investigation on the sitting condition in these premise conditions for conceptual designs of the disposal facilities.

JAEA Reports

Selection of main nuclides from the viewpoint of safety assessment for near surface disposal of low-level radioactive waste generated from research, industrial and medical facilities, 3; Preliminary selection of important radionuclides contained in low-level radioactive waste generated from major research facilities

Sakai, Akihiro; Amazawa, Hiroya; Nakata, Hisakazu; Takahashi, Kuniaki; Kihara, Shinji

JAEA-Technology 2010-021, 152 Pages, 2010/07

JAEA-Technology-2010-021.pdf:7.87MB

Total radioactivity and radioactive concentration limit of nuclides in low level radioactive waste that are expected to cause relatively large dose in near surface disposal are needed to be described in the licensing application form, as so-called "main nuclides", for disposal business of LLW generated from research, industrial and medical facilities. In this report, as an example, the main nuclides were preliminarily selected out of the nuclides contained in LLW generated from main research reactors and PIE facilities in Nuclear Science Research Institute of JAEA, by use of nuclide composition ratios in the wastes and their radioactivity concentration limit of near surface disposal derived by Nuclear Safety Commission in Japan. As results of preliminary selection of main nuclides without fixed radioactive inventory in the wastes, 24, 30 and 33 nuclides were selected as main nuclides for LLW from the reactors, PIE facilities, and both facilities, respectively.

JAEA Reports

Analysis of the radioactivity concentrations in asphalt- or cement-solidified products generated from research facilities

Hoshi, Akiko; Kameo, Yutaka; Katayama, Atsushi; Sakai, Akihiro; Tsuji, Tomoyuki; Nakashima, Mikio; Kihara, Shinji; Takahashi, Kuniaki

JAEA-Data/Code 2009-023, 84 Pages, 2010/03

JAEA-Data-Code-2009-023.pdf:12.81MB

In order to establish the practical evaluation methods such as scaling factor method to determine the radioactivity concentrations of the important nuclides for safety assessment of disposal of radioactive wastes, we analyzed low-level radioactive liquid waste (56 samples), which is generated from various research facilities at Nuclear Science Research Institute from FY1998 to FY2007 and accumulated the radioactivity concentrations data (563 data) of the 17 important nuclides. We investigated the correlation of the radioactivity concentrations of the important nuclides with the "Key nuclides ($$^{60}$$Co or $$^{137}$$Cs)". In present paper, the radioactivity concentrations data of the 17 important nuclides and the results of the correlation of the radioactivity concentrations are summarized for the data to establish the practical evaluation methods to determine the radioactivity concentrations in asphalt-solidified or cement-solidified products.

JAEA Reports

Selection of important nuclides from the viewpoint of safety assessment for disposal of radioactive waste arising from research institutes, 2; Analytical scheme for nuclide composition in radwastes arising from research and testing reactor and post-irradiation examination facilities

Asai, Shiho; Sakai, Akihiro; Yoshimori, Michiro; Kihara, Shinji

JAERI-Tech 2003-071, 46 Pages, 2003/08

JAERI-Tech-2003-071.pdf:4.31MB

As part of survey concerning radioactive inventory of radwastes arising from research institutes, an analytical scheme has been studied for verifying their nuclide composition based on calculation analysis and record, in consideration of the its characteristics. In this study, radwastes are used as samples, which arise from research and testing reactors and post-irradiation examination facilities (PIE facilities). Though separation procedures are simplified and rationalized, quantifiable values could be obtained with relative errors under 10% for almost all the samples containing nuclides like $$^{59}$$Ni and $$^{238}$$U which concentrations are low, and recoveries were high on the whole. These show that the analytical scheme is useful for chemical separation of radwastes arising from research and testing reactors and PIE facilities.

JAEA Reports

Incineration technology in combination with fluidized bed and copper oxide catalyst for spent ion exchange resins

Kihara, Shinji; Yahata, Taneaki; *; ; *; ; ; *

JAERI-Research 97-037, 43 Pages, 1997/05

JAERI-Research-97-037.pdf:1.85MB

no abstracts in English

JAEA Reports

Dechlorinating reaction of organic chlorides

Yahata, Taneaki*; Kihara, Shinji;

JAERI-Research 96-035, 24 Pages, 1996/06

JAERI-Research-96-035.pdf:0.97MB

no abstracts in English

Journal Articles

Incineration of spent ion exchange resins in combination with fluidized bed and catalyst, II

Kihara, Shinji; Yahata, Taneaki; ; Nishimura, Mitsuhiro

Incineration Conf. Proc., p.457 - 460, 1993/00

no abstracts in English

Journal Articles

Incineration of spent ion exchange resins in combination with fluidized bed and catalyst

Yahata, Taneaki; Kihara, Shinji; Hirata, Masaru; Abe, Masayoshi

1992 Incineration Conf. Proc., p.311 - 315, 1992/00

no abstracts in English

Oral presentation

Irradiation behavior of MA-containing MOX fuel, 4; Metallographic examination of Np/Am-MOX fuel irradiated for 10 min. in JOYO

Maeda, Koji; Sasaki, Shinji; Kato, Masato; Kihara, Yoshiyuki; Osato, Yukihiro*; Onuma, Yasuhiro*; Nukaga, Sadayoshi*

no journal, , 

no abstracts in English

Oral presentation

Irradiation behavior of MA-containing MOX fuel, 7; Metallographic examination of Np/Am-MOX fuel irradiated for 24 hours in JOYO

Maeda, Koji; Sasaki, Shinji; Kato, Masato; Kihara, Yoshiyuki; Osato, Yukihiro*; Onuma, Yasuhiro*; Nukaga, Sadayoshi*

no journal, , 

no abstracts in English

Oral presentation

The Project for grouting technology development for the high level radioactive waste repository, 9; Development of grout penetration model

Nobuto, Jun*; Okihara, Mitsunobu*; Kobayashi, Shinji*; Shinkai, Fumiaki

no journal, , 

no abstracts in English

Oral presentation

Results of the program to develope guidelines for decontamination, 3; Demonstration project of decontamination at Heart Land Haramachi in Minami-soma city

Amazawa, Hiroya; Sakai, Akihiro; Nakata, Hisakazu; Miyahara, Kaname; Kihara, Shinji

no journal, , 

JAEA performed decontamination experiments at a test site (Heart Land Haramachi) that combined a range of buildings and different types of land use, located in Minami Soma city as a field decontamination project in order to accumulate knowledge and data for full-scale decontamination. As a result of the decontamination that was performed using methods that can be easily implemented, taking into consideration the topography and land use of the target area, the average air dose rates were reduced to approximately one half of the values before decontamination. In addition, it was confirmed that, to reduce the exposure doses of people living in houses adjacent to a contaminated forest, a sufficient effect can be obtained by decontaminating the forest to a depth of 10 m from the forest boundary. For contaminated asphalt-paved roads, decontamination by shot blasting was effective.

Oral presentation

Results of the program to develop guidelines for decontamination, 2; Demonstration project of decontamination at Shimo-oguni area in Date city

Sakai, Akihiro; Amazawa, Hiroya; Nakata, Hisakazu; Miyahara, Kaname; Kihara, Shinji

no journal, , 

JAEA performed decontamination experiments at a test site (Shimo-oguni area) that combined a range of buildings and different types of land use, located in Date city as a field decontamination project in order to accumulate knowledge and data for full-scale decontamination. As a result of the decontamination that was performed using methods that can be easily implemented, taking into consideration the topography and land use of the target area, the average air dose rates were reduced to approximately one half of the values before decontamination. In addition, contamination state of residential house roofs showed a tendency for radiocesium to be concentrated at specific locations. It was confirmed that wiping or grinding with electric grinders, according to the contamination state, were effective means of decontaminating residential house roofs.

18 (Records 1-18 displayed on this page)
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