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Journal Articles

Application of neutron stress measurement to reinforced concrete structure

Suzuki, Hiroshi; Kusunoki, Koichi*; Kanematsu, Manabu*; Tasai, Akira*; Hatanaka, Yuichi*; Tsuchiya, Naoko*; Bae, S.*; Shiroishi, Sho*; Sakurai, Sonoko*; Kawasaki, Takuro; et al.

JPS Conference Proceedings (Internet), 8, p.031006_1 - 031006_6, 2015/09

The bond resistance between reinforcing bar (rebar) and concrete is one important parameter for examining integrity of the reinforced concrete structure, and is commonly evaluated by measuring the strain distribution along the rebar embedded in concrete. Here we present two types of applications of the time-of-flight neutron diffraction technique to measure the stress distribution of the rebar. It was demonstrated that bond deterioration around cracks developed in concrete can be evaluated by measuring the stress distribution along the embedded rebar using neutron diffraction. Furthermore, a change in the stress distribution along the rebar due to bond deterioration by corrosion was observed. The neutron diffraction technique is expected to become a novel method for measuring the stress (strain) of the rebar embedded in concrete, and will eventually provide insight into the actual phenomena on the reinforced concrete structures.

JAEA Reports

Enhancement of the methodology of repository design and post-closure performance assessment for preliminary investigation stage, 3; Progress report on NUMO-JAEA collaborative research in FY2013 (Joint research)

Shibata, Masahiro; Sawada, Atsushi; Tachi, Yukio; Makino, Hitoshi; Wakasugi, Keiichiro; Mitsui, Seiichiro; Kitamura, Akira; Yoshikawa, Hideki; Oda, Chie; Ishidera, Takamitsu; et al.

JAEA-Research 2014-030, 457 Pages, 2015/03

JAEA-Research-2014-030.pdf:199.23MB

JAEA and NUMO have conducted a collaborative research work which is designed to enhance the methodology of repository design and post-closure performance assessment in preliminary investigation stage. With regard to (1) study on rock suitability in terms of hydrology, based on some examples of developing method of hydro-geological structure model, acquired knowledge are arranged using the tree diagram, and model uncertainty and its influence on the evaluation items were discussed. With regard to (2) study on scenario development, the developed approach for "defining conditions" has been reevaluated and improved from practical viewpoints. In addition, the uncertainty evaluation for the effect of use of cementitious material, as well as glass dissolution model, was conducted with analytical evaluation. With regard to (3) study on setting radionuclide migration parameters, based on survey of precedent procedures, multiple-approach for distribution coefficient of rocks was established, and the adequacy of the approach was confirmed though its application to sedimentary rock and granitic rock. Besides, an approach for solubility setting was developed including the procedure of selection of solubility limiting solid phase. The adequacy of the approach was confirmed though its application to key radionuclides.

Journal Articles

Measuring strain and stress distributions along rebar embedded in concrete using time-of-flight neutron diffraction

Suzuki, Hiroshi; Kusunoki, Koichi*; Hatanaka, Yuichi*; Mukai, Tomohisa*; Tasai, Akira*; Kanematsu, Manabu*; Kabayama, Kenji*; Harjo, S.

Measurement Science and Technology, 25(2), p.025602_1 - 025602_8, 2014/02

 Times Cited Count:9 Percentile:58.71(Engineering, Multidisciplinary)

In the modern society, architectural and civil engineering structures such as reinforced concrete buildings require high seismic performance to minimize the "megarisk" exposed from urban earthquake hazards. In the reinforced concrete structures, the bond resistance between rebar and concrete is one important parameter for discussing its performance and it has been typically evaluated by measuring the strain distribution along the embedded rebar. Here we present an in-situ strain and stress measurements for the rebar in the reinforced concrete using time-of-flight neutron diffraction as a novel alternative technique to typical strain gauges. It was demonstrated in this study that the three-dimensional deformation behavior of the embedded rebar in normal-strength concrete, cured in air, can be accurately measured under pull-out loading using time-of-flight neutron diffraction.

Journal Articles

Characterization of the dissolver sludge of MOX spent fuel at the Tokai Reprocessing Plant

Suzuki, Kazuyuki; Hatanaka, Akira; Samoto, Hirotaka; Suwa, Toshio; Tanaka, Kosuke; Tanaka, Yukiyoshi

Proceedings of International Conference on Toward and Over the Fukushima Daiichi Accident (GLOBAL 2011) (CD-ROM), 6 Pages, 2011/12

The properties of the sludge in dissolver vessels from the reprocessing of ATR-MOX and ATR-UO$$_{2}$$ fuels were investigated on the pilot-plant scale at the Tokai Reprocessing Plant (TRP). This sludge is mainly composed of platinum-group elements, zircaloy fragments, and post-precipitates from the dissolver solution. The sludge deposited on the dissolver causes difficulties such as pipe clogging. The characteristics of the sludge collected from the dissolver vessels, which affect the reprocessing operation, were revealed through chemical composition analysis using ICP-AES, and XRD. It was confirmed that the major component of the sludge was zirconium molybdate, and no significant differences between ATR-MOX and ATR-UO$$_{2}$$ fuels were observed in terms of the sludge compositions. In order to gain further understanding of the properties of the sludge, the distributions of Pu and other trace elements were EPMA.

Journal Articles

Mix design of low pH cement shotcrete in high level radioactive waste repositories

Noguchi, Akira; Kishi, Hirokazu; Hatanaka, Koichiro; Naito, Morimasa

Proceedings of 19th International Conference on Nuclear Engineering (ICONE-19) (CD-ROM), 6 Pages, 2011/10

A standardized method for choosing a mix design of low pH shotcrete is proposed for their intended use in the construction of a High Level Radioactive Waste (HLW) repository in order to be applied to the various geological environment of the location of the HLW repositories. There are two improvement in this method. One is estimating binder composition to satisfy low pH. The other is estimating water bender ratio to satisfy the strength of sprayed concrete. The method uses a sequential development process with consideration given to a number of physicochemical requirements, incorporates current shotcrete technology. The method is demonstrated in its entirety through a series of experiments and tests using a low pH cement binder comprised of a mixture of ordinary Portland cement, fly ash (FA) and silica fume (SF), referred to here as high-volume FA SF cement (HFSC). Moreover, the method is referred from the demonstration of HFSC shotcrete in Horonobe underground research laboratory.

Journal Articles

Neutron energy spectra at 180$$^{circ}$$ from 140 MeV proton incident reactions

Iwamoto, Yosuke; Satoh, Daiki; Nakane, Yoshihiro; Nakashima, Hiroshi; Endo, Akira; Sakamoto, Yukio; Hagiwara, Masayuki*; Iwase, Hiroshi*; Yashima, Hiroshi*; Tamii, Atsushi*; et al.

Journal of the Korean Physical Society, 59(2), p.1753 - 1756, 2011/08

 Times Cited Count:2 Percentile:20.16(Physics, Multidisciplinary)

Neutron production cross sections of carbon and iron targets for 140 MeV proton at 180$$^{circ}$$ were measured at the RCNP cyclotron facility. The neutron energy spectra were obtained by using the time-of-flight technique in the energy range above 1 MeV. The results of carbon and iron targets were compared with experimental data for 113 MeV (p,xn) reactions at 150 deg by Meier et al. Our data gave good agreements with them in spite of different incident energies and angles. Calculations were performed with different intranuclear cascade models (Bertini, ISOBAR, and JQMD) implemented in the PHITS code. Calculated results with the ISOBAR and JQMD models roughly agreed with the experimental data for iron targets, although Bertini could not reproduce the high energy neutrons above 10 MeV.

Journal Articles

Experimental method for neutron elastic scattering cross-section measurement in intermediate energy region at RCNP

Satoh, Daiki; Iwamoto, Yosuke; Hagiwara, Masayuki*; Iwase, Hiroshi*; Yashima, Hiroshi*; Sanami, Toshiya*; Sato, Tatsuhiko; Endo, Akira; Sakamoto, Yukio; Nakane, Yoshihiro; et al.

Progress in Nuclear Science and Technology (Internet), 1, p.20 - 23, 2011/02

An experimental method and data processing procedure have been developed for the measurement of neutron elastic scattering cross sections in intermediate energy region above 100 MeV. The data were obtained at Research Center for Nuclear Physics (RCNP) in Osaka University by utilizing a $$^{7}$$Li(p,n) quasi-monoenergetic neutron source and Time-of-Flight (TOF) technique.

Journal Articles

Measurement of neutron elastic scattering cross sections for carbon at 134 MeV

Satoh, Daiki; Iwamoto, Yosuke; Hagiwara, Masayuki*; Iwase, Hiroshi*; Yashima, Hiroshi*; Sato, Tatsuhiko; Endo, Akira; Sakamoto, Yukio; Nakane, Yoshihiro; Nakashima, Hiroshi; et al.

Radiation Measurements, 45(10), p.1159 - 1162, 2010/12

 Times Cited Count:1 Percentile:9.99(Nuclear Science & Technology)

Elastic neutron-scattering cross sections for carbon nucleus have been measured by using 134-MeV monoenergetic neutron beam in Research Center for Nuclear Physics (RCNP), Osaka University. The measured angles were set at 6$$^{circ}$$, 8$$^{circ}$$, and 15$$^{circ}$$ in laboratory system. The liquid organic scintillators, whose size is 12.7 cm in diameter and 12.7 cm in thickness, were mounted at each angle as neutron detector. In the off-line analysis, the events of elastic-neutron scattering were extracted on basis of the Time-of-Flight (TOF) information. The results were compared with the data measured by the groupe of U.C. Davis with a recoil proton spectrometer and the evaluations of the nuclear data libraries, JENDL/HE-2007 and ENDF/B-VII.0. Our results show a good agreement with the data of U.C. Davis. This indicates that our experimental method based on the TOF teqnique is appropriate to the measurement of elastic neutron-scattering cross section in this energy region. In addition, we exhibit that the data of ENDF/B-VII.0 represent the experimental data, but JENDL/HE-2007 underestimates about 30$${%}$$ in the forward angle region.

Journal Articles

Measurements and Monte Carlo calculations of neutron production cross-sections at 180$$^{circ}$$ for the 140 MeV proton incident reactions on carbon, iron, and gold

Iwamoto, Yosuke; Satoh, Daiki; Hagiwara, Masayuki*; Yashima, Hiroshi*; Nakane, Yoshihiro; Tamii, Atsushi*; Iwase, Hiroshi*; Endo, Akira; Nakashima, Hiroshi; Sakamoto, Yukio; et al.

Nuclear Instruments and Methods in Physics Research A, 620(2-3), p.484 - 489, 2010/08

 Times Cited Count:8 Percentile:51.6(Instruments & Instrumentation)

The neutron production cross sections of carbon, iron, and gold targets with 140 MeV protons at 180$$^{circ}$$ were measured at the RCNP cyclotron facility. The time-of-flight technique was used to obtain the neutron energy spectra in the energy range above 1 MeV. The carbon and iron target results were compared with the experimental data from 113 MeV (p,xn) reactions at 150$$^{circ}$$ reported by Meier et al. Our data agreed well with them in spite of different incident energies and angles. Calculations were then performed using different intra-nuclear cascade models (Bertini, ISOBAR, and JQMD) implemented with PHITS code. The results calculated using the ISOBAR and JQMD models roughly agreed with the experimental iron and gold target data, but the Bertini could not reproduce the high energy neutrons above 10 MeV.

Oral presentation

Measurement of elastic neutron-scattering cross sections in intermediate energy region

Satoh, Daiki; Iwamoto, Yosuke; Sato, Tatsuhiko; Endo, Akira; Sakamoto, Yukio; Nakane, Yoshihiro; Nakashima, Hiroshi; Hagiwara, Masayuki*; Iwase, Hiroshi*; Yashima, Hiroshi*; et al.

no journal, , 

Elastic neutron-scattering cross sections for carbon nucleus have been measured by using 134-MeV monoenergetic neutron beam in Research Center for Nuclear Physics (RCNP), Osaka University. The measured angles were set at 6$$^{circ}$$, 8$$^{circ}$$, and 15$$^{circ}$$ in laboratory system. The liquid organic scintillators, whose size is 12.7 cm in diameter and 12.7 cm in thickness, were mounted at each angle as neutron detector. In the off-line analysis, the events of elastic-neutron scattering were extracted on basis of the Time-of-Flight (TOF) information. The results were compared with the data measured by the group of U.C. Davis with a recoil proton spectrometer and the evaluations of the nuclear data libraries, JENDL/HE-2007 and ENDF/B-VII.0. Our results show a good agreement with the data of U.C. Davis. This indicates that our experimental method based on the TOF technique is appropriate to the measurement of elastic neutron-scattering cross section in this energy region.

Oral presentation

Dissolution test on the sludge of the dissolver

Sugai, Eiji; Terunuma, Hirotaka; Otani, Takehisa; Hikita, Keiichi; Hatanaka, Akira; Samoto, Hirotaka; Okano, Masanori; Hayashi, Shinichiro

no journal, , 

A dissolution test of the sludge gathered from the dissolver of Tokai Reprocessing Plant (TRP) was performed for the purpose of eliminating of the sludge, which deposited in the dissolver and clogged pipes equipped in the dissolver. In the result, the sludge consisted primarily of ZrMo$$_{2}$$O$$_{7}$$(OH)$$_{2}$$(H$$_{2}$$O)$$_{2}$$ and was possible to eliminate at the rate of about 80% by using NaOH and HNO$$_{3}$$ reagent which was commonly-used in the PUREX process. From this experimental result, it is thought that the method of using NaOH and HNO$$_{3}$$ reagent is effective method for the elimination of the sludge which deposited in the dissolver.

Oral presentation

Replacement of butterfly valves installed in shearing off-gas treatment process of TRP, 2; Survey results of replaced valves

Sugai, Eiji; Kikuchi, Hideki; Hatanaka, Akira; Otani, Takehisa; Suzuki, Kazuyuki; Taguchi, Katsuya

no journal, , 

no abstracts in English

Oral presentation

Performance examinations of DARWIN at high-energy neutron fields in RCNP

Sato, Tatsuhiko; Satoh, Daiki; Endo, Akira; Iwamoto, Yosuke; Iwase, Hiroshi*; Hagiwara, Masayuki*; Nakamura, Takashi*; Tamii, Atsushi*; Shima, Tatsushi*; Hatanaka, Kichiji*

no journal, , 

We developed a dose and spectrum monitoring system applicable to neutrons, photons and muons over wide energy ranges, and designated it as DARWIN. The system consists of a phoswitch-type scintillation detector, a data-acquisition (DAQ) module for digital waveform analysis, and a personal computer equipped with a graphical-user-interface (GUI) program for controlling the system. The performance of DARWIN was examined at high-energy neutron fields in Research Center for Nuclear Physics (RCNP) at Osaka University. The details of the profiles of DARWIN as well as the results of its performance examinations will be described at the meeting.

Oral presentation

Development of the Integrated System for Repository Engineering (ISRE), 1; Conceptual design of the ISRE utilizing CIM technology

Sugita, Yutaka; Chijiwa, Tatsunori; Honda, Akira; Shibata, Masahiro; Kawaguchi, Tatsuya; Maekawa, Keisuke; Hatanaka, Koichiro; Ebashi, Takeshi; Semba, Takeshi; Makino, Hitoshi

no journal, , 

This paper reports on the development of ISRE (the Integrated System for Repository Engineering), as a knowledge management tool on repository design and engineering technology, which manages and inherits the information and knowledge of each phase of the disposal project of radioactive waste lasting around 100 years, and which also enables reasonable design of the repository by using accumulated and integrated information. The content of this paper is the conceptual design of the ISRE utilizing CIM (Computer Information Modeling) technology.

Oral presentation

Remote wall thickness measurement of the fuel basket of the dissolver

Yokota, Satoru; Hatanaka, Akira; Fujimori, Masahito; Shimoyamada, Tetsuya; Nakamura, Yoshinobu

no journal, , 

Three batch-type dissolvers in the Tokai Reprocessing Plant are a device for dissolving spent fuel. The dissolver is composed of one slab and two barrels (stainless steel 310s). Install a fuel basket (stainless steel 304L) in the barrel and accept the sheared spent fuel to dissolve it. The insoluble fuel cladding is taken out of the barrels with the basket. The dissolution time of operation for one batch is approximately 10 hours. During dissolution operation, nitric acid was added to the dissolver into the spent fuel in the basket with water. The solution was heated with steam. Corrosion failure has occurred in the past because the dissolver is exposed to a high corrosive environment (high temperature, high acid concentration). Therefore, we carry out the periodical wall thickness measurement of the barrel by the remote control. On the other hand, the wall thickness measurement of the fuel basket was carried out only once by destructive measurement at the time of renewal in 1999. The details of the corrosion tendency of the fuel basket are unknown, and it is urgent to establish a non-destructive measurement method by remote handling. Therefore, we examined the method of wall thickness measurement of the fuel basket and established the measuring technique.

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