Refine your search:     
Report No.
 - 
Search Results: Records 1-8 displayed on this page of 8
  • 1

Presentation/Publication Type

Initialising ...

Refine

Journal/Book Title

Initialising ...

Meeting title

Initialising ...

First Author

Initialising ...

Keyword

Initialising ...

Language

Initialising ...

Publication Year

Initialising ...

Held year of conference

Initialising ...

Save select records

JAEA Reports

Radiation monitoring using manned helicopter around the nuclear power station in the fiscal year 2015 (Contract research)

Sanada, Yukihisa; Munakata, Masahiro; Mori, Airi; Ishizaki, Azusa; Shimada, Kazumasa; Hirouchi, Jun; Nishizawa, Yukiyasu; Urabe, Yoshimi; Nakanishi, Chika*; Yamada, Tsutomu*; et al.

JAEA-Research 2016-016, 131 Pages, 2016/10

JAEA-Research-2016-016.pdf:20.59MB

By the nuclear disaster of Fukushima Daiichi Nuclear Power Station (FDNPS), Tokyo Electric Power Company (TEPCO), caused by the East Japan earthquake and the following tsunami occurred on March 11, 2011, a large amount of radioactive materials was released from the NPS. After the nuclear disaster, airborne radiation monitoring using manned helicopter was conducted around FDNPS. In addition, background dose rate monitoring was conducted around Sendai Nuclear Power Station. These results of the aerial radiation monitoring using the manned helicopter in the fiscal 2015 were summarized in the report.

Journal Articles

Introduction to plasma fusion energy

Takamura, Shuichi*; Kado, Shinichiro*; Fujii, Takashi*; Fujiyama, Hiroshi*; Takabe, Hideaki*; Adachi, Kazuo*; Morimiya, Osamu*; Fujimori, Naoji*; Watanabe, Takayuki*; Hayashi, Yasuaki*; et al.

Kara Zukai, Purazuma Enerugi No Subete, P. 164, 2007/03

no abstracts in English

Oral presentation

CREPT-MCNP; Code system for efficiency calibration of $$gamma$$-ray spectrometer based on the representative point method

Saegusa, Jun; Ogose, Hitoshi; Takamura, Atsushi*; Sugita, Takeshi*

no journal, , 

The representative point method is an efficiency calibration method for a $$gamma$$-ray spectrometer. A calculation code system, CREPT-MCNP, for implementing the method has been newly developed. CREPT-MCNP can be operated under the Windows PC environment as a GUI based application. The code system estimates the position of the representative point which is intrinsic to each shape of volume sample, and also gives the self-absorption factors to make correction on the efficiencies measured at the representative point with a standard point source. It can deal with photons between 20 keV and 2 MeV with p- or n-type germanium semiconductor detectors.

Oral presentation

Development and production of cables for ITER

Takahashi, Yoshikazu; Nabara, Yoshihiro; Nunoya, Yoshihiko; Suwa, Tomone; Tsutsumi, Fumiaki; Oshikiri, Masayuki; Ozeki, Hidemasa; Shibutani, Kazuyuki*; Kawano, Katsumi; Kawasaki, Tsutomu*; et al.

no journal, , 

Japan Atomic Energy Agency (JAEA) is procuring all amounts of Nb$$_{3}$$Sn conductors for Central Solenoid (CS) in the ITER project. Before start of mass-productions, the conductor should be tested to confirm superconducting performance in the SULTAN facility, Switzerland. The cable with a shorter twist pitch shows no degradation of Tcs against to electromagnetic load cycles. However, it is difficult to make the cable, because the diameter of the cable with shorter twist pitch is larger and the cable has to compact more. The technology for the cables with STP was developed in Japanese cabling suppliers. The several key technologies and production will be described in this paper.

Oral presentation

Study on inhibition of pressure fluctuation induced by separation vortex shedding in primary cold-leg piping of sodium cooled fast reactor

Mizutani, Jun*; Takamura, Hiroyuki*; Ebara, Shinji*; Hashizume, Hidetoshi*; Yamano, Hidemasa

no journal, , 

In cold leg piping of primary cooling system of Japan Sodium-cooled Fast Reactor (JSFR), high Reynolds (Re) number and three dimensional arrangement of 3 elbow structure forms complex turbulent flow field, and pressure fluctuation induced by separation vortex release is postulated. inhibition of the separation is considered to lower the pressure fluctuation and changing inflow condition indicated possibility of inhibiting pressure fluctuation. In this study, 1/7 scale flow testing device simulating JSFR primary cold-leg piping was used to study conditions to reduce separation.

Oral presentation

Technical problem and resolution of superconductor for the ITER magnet

Nunoya, Yoshihiko; Nabara, Yoshihiro; Takahashi, Yoshikazu; Oshikiri, Masayuki; Tsutsumi, Fumiaki; Takamura, Jun; Chuheishi, Shinji; Shibutani, Kazuyuki*

no journal, , 

Japan Atomic Energy Agency is responsible for Nb$$_{3}$$Sn Cable-in-Conduit conductors or the Central Solenoid (CS) and the Toroidal Field (TF) coil under the ITER project. Full-size conductor test was performed to confirm performance using SULTAN facility at Switzerland, especially effect of electromagnetic load cycles on the current sharing temperature (Tcs). The original (reference) conductor which had relatively long twist pitch cabling design is called as the normal twist pitch (NTP) conductor. NTP conductor showed Tcs decrease with increasing the number of cycles. By introducing short twist pitch conductor, performance during electromagnetic cycles was improved and concern of Tcs decrease in ITER CS is eliminated. Improvement is understood that shorting pitch of the triplet in the first stage make more engagement of strand providing more stiffness of the cable that prevent strand deformation like buckling observed in the destructive examination of the previous SULTAN sample.

Oral presentation

Progress of ITER conductor fabrication

Nunoya, Yoshihiko; Takahashi, Yoshikazu; Oshikiri, Masayuki; Tsutsumi, Fumiaki; Nabara, Yoshihiro; Takamura, Jun; Chuheishi, Shinji; Shibutani, Kazuyuki*; Suwa, Tomone; Matsuda, Hidemitsu*

no journal, , 

no abstracts in English

Oral presentation

Non-destructive examination of jacket sections for ITER central solenoid (CS) coil

Takahashi, Yoshikazu; Suwa, Tomone; Nabara, Yoshihiro; Ozeki, Hidemasa; Nunoya, Yoshihiko; Oshikiri, Masayuki; Tsutsumi, Fumiaki; Takamura, Jun; Shibutani, Kazuyuki*; Chuheishi, Shinji; et al.

no journal, , 

The Japan Atomic Energy Agency (JAEA) is responsible for procuring all amounts of Central Solenoid (CS) Conductors for ITER, including CS jacket sections. The conductor is cable-in-conduit conductor (CICC) with a central spiral. A total of 576 Nb$$_{3}$$Sn strands and 288 copper strands are cabled around the central spiral. The maximum operating current is 40 kA at magnetic field of 13 T. CS jacket section is circular in square type tube made of JK2LB, which is high manganese stainless steel with boron added. Unit length of jacket sections is 7 m and 6,300 sections will be manufactured and inspected. Outer/inner dimension and weight are 51.3/35.3 mm and around 90 kg, respectively. Eddy Current Test (ECT) and Phased Array Ultrasonic Test (PAUT) were developed for non-destructive examination. The defects on inner and outer surfaces can be detected by ECT. The defects inside jacket section can be detected by PAUT. These technology and the inspected results are reported in this paper.

8 (Records 1-8 displayed on this page)
  • 1