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Journal Articles

Review of the performance of a car-borne survey system, KURAMA-II, used to measure the dose rate after the Fukushima Dai-ichi Nuclear Power Plant accident

Tsuda, Shuichi; Tanigaki, Minoru*; Yoshida, Tadayoshi; Saito, Kimiaki

Hoshasen, 44(3), p.109 - 118, 2018/11

JAEA has started to perform dose rate monitoring using a car-borne survey system KURAMA to rapidly produce the dose rate mappings of the deposited radionuclides in the environment after the Fukushima Dai-ichi Nuclear Power Plant accident. KURAMA is a car-borne survey system developed by Kyoto University to perform dose rate monitoring in a wide area in detail with rapidity. By improving KURAMA with continuous dose rate monitoring, the 2nd generation of KURAMA (KURAMA-II) succeeded in downsizing, durability and automated transmission of data so that enable detailed dose rate mapping in wide area in shorter period of time. This paper reports the radiation characteristics and the simulation analysis of KURAMA-II on the special issue of Hoshasen, the journal of Ionization Radiation Division in the Japan society of applied physics.

Journal Articles

Dose measurement at high dose rate region by fricke dosimeter

Yamamoto, Tadatoshi;

Radioisotopes, 31(3), p.148 - 151, 1982/00

no abstracts in English

Journal Articles

A simple method of low X and $$gamma$$ dose rate measurement by planer-type silicon solar cell

; *

Denki Gakkai Rombunshi, C, 97(11), p.215 - 222, 1977/11

no abstracts in English

Journal Articles

A Solid-state ionization chamber for the high-dose-rate measurement of gamma-rays

; ; *

Int.J.Appl.Radiat.Isot., 24(11), p.627 - 637, 1973/11

no abstracts in English

JAEA Reports

Manual of Gamma-Ray Dosimetry Using an Ionization Chamber

JAERI-M 4886, 13 Pages, 1972/07

JAERI-M-4886.pdf:0.65MB

no abstracts in English

Oral presentation

Intercomparison of dose rates obtained from scintillation detectors with different shape in the environmental monitoring, 1; Experiments

Yoshida, Tadayoshi; Tsuda, Shuichi; Tanigaki, Minoru*; Okumura, Ryo*; Saito, Kimiaki

no journal, , 

no abstracts in English

Oral presentation

Feasibility study of technology for Pu solution monitoring including FP, 2; Dose rate distribution measurement test inside the cell storing HAW tank

Tokoro, Hayate; Suzuki, Satoshi*; Miyoshi, Ryuta; Sakurai, Yasuhiro; Matsuki, Takuya; Tsutagi, Koichi; Sekine, Megumi; Shimizu, Yasuyuki; Nakamura, Hironobu

no journal, , 

We inserted a newly designed and manufactured thruster into the guide tube of the high active liquid waste storage cell for inspection in the Tokai Reprocessing Plant and measured the dose rate inside the cell. The dose rate distribution measurements using thruster is an unprecedented experiment, we checked job safety, operability of an equipment and relationship between insert distance of dosimeter and measurement position by using isometric scale mock-up equipment in advance. As a result, we implemented dose rate distribution measurement test inside the cell.

Oral presentation

Measurement and analysis of in-vessel component activation and $$gamma$$ dose rate distribution in Joyo

Yamamoto, Takahiro; Maeda, Shigetaka; Ito, Chikara

no journal, , 

In the experimental fast reactor Joyo, the damaged upper core structure (UCS) was retrieved into the cask in May 2014 for its replacement as a part of the restoration work of the incident concerning with the irradiation test sub-assembly named MARICO-2. The dose rate on UCS surface was quite high due to the activation for over 30 years operation. In order to attain the optimum safety design, manufacture and operation of equipment for UCS replacement, the method to evaluate UCS surface dose rate was developed on the basis of C/E obtained by the in-vessel dose rate measurement in Joyo. In order to verify the evaluation method, the axial $$gamma$$-ray distribution measurement on the surface of the cask, which contained UCS, was conducted using a plastic scintillating optical fiber (PSF) detector. As a result, the measured axial $$gamma$$-ray distribution on the cask surface had a peak on proper location with considering the cask shielding structure and agree well with the calculated distribution and the C/E of axial $$gamma$$-ray distribution on the cask surface was ranged from 1.1 to 1.7. It was confirmed that the calculation for UCS replacement equipment design had a margin of conservatively. Then, the results showed that the applied evaluation method for UCS replacement equipment design was sufficiently reliable. In the in-vessel repair work for sodium cooled fast reactors (SFRs), the design and work condition estimation are important. The accumulated experience provides valuable insights into further improvements for in-vessel repair techniques in SFRs.

Oral presentation

Characterization of TOF scintillation fiber radiation sensor for high dose rate measurement

Terasaka, Yuta; Sato, Yuki; Watanabe, Kenichi*; Uritani, Akira*; Torii, Tatsuo

no journal, , 

no abstracts in English

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