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Journal Articles

Feasibility study of technology for Pu solution monitoring including FP; Development of gamma spectra detector for high active liquid waste

Sekine, Megumi; Matsuki, Takuya; Tokoro, Hayate; Tsutagi, Koichi; Kitao, Takahiko; Nakamura, Hironobu; Tomikawa, Hirofumi

Proceedings of INMM 59th Annual Meeting (Internet), 10 Pages, 2018/07

In a reprocessing facility, it is necessary to develop a detector which can measure plutonium (Pu) content in the Pu solutions containing fission products (FP) in order to expand the application of Pu monitoring. In order to establish this technology, JAEA has studied a system measure $$gamma$$-rays was utilized since it applicable for Pu monitoring. Ce:GAGG (Ce:Gd$$_{3}$$Al$$_{2}$$Ga$$_{3}$$O$$_{12}$$) scintillator detector can measure a wide energy range in a high-dose environment and has reasonable resolution. $$gamma$$-ray measurements were performed inside of the concrete cell containing the High Active Liquid Waste tank at the Tokai reprocessing plant. In the spectra, the two significant peaks were measured by the GAGG above 800 keV and were considered to be from Eu-154. There $$gamma$$-ray measurements will be combined with previous neutron measurements and both will be compared to MCNP models for future Pu monitoring technology. This presentation will describe the detector selection, the design system, the results of $$gamma$$-ray spectral measurements and the applicability for Pu monitoring. This project has been carried out under the support of the Ministry of Education, Culture, Sports, Science and Technology (MEXT) of the Japanese government.

Journal Articles

Feasibility study of technology for Pu solution monitoring including FP; Design of GAGG detector and gamma spectrum measurement

Sekine, Megumi; Matsuki, Takuya; Tokoro, Hayate; Tsutagi, Koichi; Tomikawa, Hirofumi; Nakamura, Hironobu

Nihon Kaku Busshitsu Kanri Gakkai Dai-38-Kai Nenji Taikai Rombunshu (Internet), 9 Pages, 2018/04

In a reprocessing facility, it is necessary to develop a detector which is measurable plutonium (Pu) amount in the Pu solution containing the Fission Product (FP) in order to expand the application of Pu monitoring. To investigate $$gamma$$ rays which is applicable for Pu monitoring, Ce:GAGG (Ce: Gd$$_{3}$$Al$$_{2}$$Ga$$_{3}$$O$$_{12}$$) scintillator which can measure a wide range of energy at high dose and has high resolution (Target: High Active Liquid Waste (HALW)) was newly designed and developed in deal with aim for Pu quantitativeness. $$gamma$$ ray measurement was performed to the HALW in the concrete cell using the detector, and it was confirmed that high energy $$gamma$$ rays (9.5 MeV) could be measured and high energy $$gamma$$ rays spectra over 3 MeV without deriving from FP at the first time. In this presentation, detector design, results of $$gamma$$ ray spectra measurement, applicability evaluation to Pu monitoring and the future plan are presented. This project has been carried out under the support of the Ministry of Education, Culture, Sports, Science and Technology (MEXT) of the Japanese government.

Oral presentation

Emergency safety measures at the Tokai Reprocessing, 1

Kishi, Yoshiyuki; Yasuda, Takeshi; Tokoro, Hayate; Yamanaka, Atsushi; Tsutagi, Koichi; Shirato, Yoji; Tanaka, Hitoshi

no journal, , 

High active liquid waste is stored in the facility equipped with cooling system and hydrogen scavenging system because of hydrogen generation due to radiolysis, and heat generation due to decay heat. The facilities related to these systems maintenance have been designed to be fed by emergency power generators in the conventional design. In addition to that, in light of the lessons learned from accident at the Fukushima Daiichi Nuclear Power Plant, we took safety measures for emergencies such as securement of the power supply system from power source vehicle to enable a quick recovery in the case of station black out in the Tokai Reprocessing Plant.

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

Feasibility study of technology for Pu solution monitoring including FP, 3; Result of $$gamma$$-ray dose rate measurement inside the cell

Sekine, Megumi; Suzuki, Satoshi*; Tokoro, Hayate; Sakurai, Yasuhiro; Miyoshi, Ryuta; Matsuki, Takuya; Yasuda, Takeshi; Tsutagi, Koichi; Nakamura, Hironobu; Tomikawa, Hirofumi

no journal, , 

JAEA is being conducted feasibility study of technology for Pu solution monitoring including fission products (FPs) as a joint research program with U.S. DOE at the High Active Liquid Waste (HALW) Storage Facility in Tokai Reprocessing Plant to address effective and efficient safeguards for reprocessing facilities. This time, calibration for Ion chamber, measurement results of $$gamma$$ ray dose rate with Ion chamber and applicability to monitoring technology will be reported.

Oral presentation

Approaches for observation inside the cell storing HAW tank at TRP

Tokoro, Hayate; Miyoshi, Ryuta; Matsuki, Takuya; Yasuda, Takeshi; Tsutagi, Koichi

no journal, , 

High active liquid waste (HAW) of about 340 m$$^{3}$$ is stored in the HAW tanks at the Tokai Reprocessing Plant. However there is no effective observation method inside the cell installing the HAW tank since no one can enter because of its high dose rate. This time, by utilizing the existing guide rail, design and manufacture of the new device for observation, optimization of the device by mockup, inside the cell observation and dose rate distribution measurement inside the cell were conducted. As the result, we were succeeded in observation of the HAW tank and measurement of the dose rate distribution inside the cell for the first time. Here we report the results of those approaches.

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