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Takemura, Morio*
JNC TJ9450 2000-002, 112 Pages, 2000/03
JNC-TJ9450-2000-002.pdf:2.55MB
This report is intended to make it easier to apply the measured data obtained from the Gap Streaming Experiment, which was conducted at the Oak Ridge National Laboratory (ORNL) during about two months beginning at the start of March, 1992 as the sixth one of a series of eight experiments planned for the Japanese-American Shielding Program for Experimental Research (JASPER) which was started in 1986. For this reason. the information presented includes specifications and measurement data for all configurations, compositions of all materials, characteristics of the measurement system. and daily-basis records of measurements. The Gap Streaming Experiment was planned to obtain the data of neutron streaming characteristics in the inclosure system above the core of an advanced fast reactor for verification and improvement of the analysis method to be applied to the shielding design. A iron-lined solid or slit concrete assembly was placed, with or without a spectrum modifier forming soft incident neutron spectrum, behind the TSR-II reactor of Tower Shielding Facility. Inserting central cylinders and cylindrical sleeves gave various gap width and offset in the slit concrete assembly. Neutron flux was measured behind the configurations with various types of detectors. The integral neutron flux in wide energy region was measured on radial traverse and on the axis behind the concrete assembly in almost all configurations. Neutron spectrum and fine radial distribution in high energy region was measured further in case of hard incident neutron spectrum, Information presented in this report is based mainly on a report issued by ORNL (ORNL/TM-12140. "Measurements for the JASPER Program Gap Streaming Experiment"). Additional information reported by the assignee is utilized also.
*; Takemura, Morio*
JNC TJ9440 2000-005, 157 Pages, 2000/03
With use of the two-dimensional discrete ordinates code DORT and the standard groupwise shielding design library JSSTDL produced from the latest evaluated nuclear data library JENDL-3.2, experimental analyses for the representative configurations in the Radial Shield Attenuation Experiment of the JASPER were performed. The results were compared with those obtained with use of traditional method DOT3.5/JSDJ2 for the previous JASPER experimetal analyses. In general, the change of the cross section library gives higher results and the change of the transport code gives lower results. Finally the new analysis method gives better agreement with the experimental results and also less deviations of calculational errors between various detectors. Experimental analyses for the thick concrete configulation in the Gap Streaming Experiment of the JASPER was also performed with the new analysis method, after solving the poor agreement found in last year with the original JASPER experimental analyses. The same tendency due to the library change was confirmed with the above mentioned analyses of the Radial Shield Attenuation Experiment. Compilation of the input data necessary for future reanalyses of important configurations in JASPER experiments were continued through the above-mentioned experimental analyses and related informations were added for repletion of the database preserved in a computer disk holding previously accumulated data. Input data descriptions were made for auxiliary routines needed for the experimental analyses and their sample data were compiled and stored in the database.
Udagawa, Akira; *; *; *; Seguchi, Tadao
JAERI-Tech 99-022, 31 Pages, 1999/03
no abstracts in English
-ray irradiated epoxy-coated reinforcing steel bar*; Akutsu, Yoichi; Okawa, Yoshinao; Suzuki, Hideyuki; *; *; *
Nihon Kenchiku Gakkai Taikai Gakujutsu Koen Kogaishu, 0, p.907 - 908, 1994/09
no abstracts in English
Iriya, Keishiro*; *
PNC TJ1201 94-004, 335 Pages, 1994/03
no abstracts in English
Iriya, Keishiro*; Fujiwara, Yasushi*; Motohashi, Kenichi*; Nakanishi, Masatoshi*
PNC TJ1449 93-001, 341 Pages, 1993/03
None
Akutsu, Yoichi; Okawa, Yoshinao; ; *
Konkurito Kogaku Rombunshu, 3(1), p.65 - 76, 1992/01
no abstracts in English
Akutsu, Yoichi; Okawa, Yoshinao; *; *
Konkurito Kogaku Nenji Rombun Hokokushu, 14(1), p.775 - 776, 1992/00
no abstracts in English
Akutsu, Yoichi; Okawa, Yoshinao; *; *
Transactions of the Japan Concrete Institute,Vol. 14, p.217 - 230, 1992/00
no abstracts in English
Obayashi Corporation*; Kajima Corporation*; Shimizu Corporation*; Taisei Corporation*
PNC TJ1449 91-006, 68 Pages, 1991/01
None
*; Himeno, Yoshiaki; *
PNC TN9410 87-168, 65 Pages, 1987/12
In the event of a design basis sodium leak accident in the reactor building of the FBRs, the leaked sodium is collected and stored in a sodium storage room until the accident comes to an end. By placing the emphasis on the heat release characteristics of the sodium storage room, the following tests were performed. (1)Determination of thermal properties of materials for the floor of the room; perlite concrete, structural concrete, etc. (2)Partial engineering tests of heat conduction from a hot sodium to structural concrete simulating the accident conditions of the floor. In the former tests, the reliable data of the thermal properties were obtained. In the latter tests, transient temperature distributions were obtained.Comparison of these distributions with the calculated results of the code indicated that the code gives conservative results.
; ; Okamoto, Yoshizo;
Keikinzoku Yosetsu, 25(9), p.29 - 39, 1987/09
no abstracts in English
Furusawa, Akinori; Nishimura, Akihiko; Takenaka, Yusuke*
no journal, ,
Large number of concrete structures built in the era of rapid economic growth will exceed fifteen years old in next 10 to 20 years. Developing maintenance and health monitoring techniques for these existing concrete structures is inevitable problem to be resolved. JAEA have tackled to that problem on collaborative research, having achieved to crack detection technique for surface on the concrete of railroad tunnel (1). The technique reported in ref. (1), however, is focusing on the surface cracks, not taking into account the condition of the deep region, including a steel reinforcing bar (rebar) in a reinforced concrete structure. This work supposes a new approach for detecting deteriorated rebar in concrete structure based on laser-ultrasonic. Irradiating the one end of a rebar by nanosecond laser pulses repetitively generates ultrasonic wave propagating along it. The waveform of the ultrasonic received the other end is analyzed to extract the information about its condition.
Okuda, Yukihiko; Kang, Z.; Nishida, Akemi; Tsubota, Haruji; Li, Y.
no journal, ,
When a projectile collides with a building of a nuclear facility, the stress waves generated at the time of the impact propagate from the impacted wall to the inside of the building. This stress wave may excite vibrations including high frequencies in the building, and it is an issue to evaluate the influence on safety related equipment. In this study, in order to contribute to the assessment of effects on internal equipment in the building, we will obtain data related to stress wave propagation in the building and the impact response of internal equipment, and develop an impact response analysis method considering the coupling of the building and the equipment. At first a projectile impact test with a building including a pseudo equipment will be conducted to investigate the stress wave propagation characteristics inside the building and the impact response characteristics of the pseudo equipment inside the building. In this paper, we will report the outline of the target test specimen of the projectile impact test, the test method and the test results.
