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Journal Articles

Feasibility study of advanced measurement technology for solution monitoring at reprocessing plant; Dose rate measurement for the solution including Pu with FP

Matsuki, Takuya; Yamanaka, Atsushi; Sekine, Megumi; Suzuki, Satoshi*; Yasuda, Takeshi; Tsutagi, Koichi; Tomikawa, Hirofumi; Nakamura, Hironobu; LaFleur, A. M.*; Browne, M. C.*

Proceedings of INMM 58th Annual Meeting (Internet), 8 Pages, 2017/07

The Tokai Reprocessing Plant (TRP) has been developing a new detector from 2015 to 2017 for purpose to monitor Pu amount in High Active Liquid Waste (HALW) containing FP. It can make a contribution to an advanced approach to effectively and efficiently conduct safeguards for reprocessing facilities because it becomes available to monitor and verify nuclear material movement continuously by a new detector, which has proposed by IAEA. For the second step of this project, we conducted dose rate measurement on the guide rail installing in the cell storing the HALW tank and comparison between measured dose rate distribution and calculation result by MCNP simulation in order to investigate the dose rate distribution which is needed for shielding design of a new detector that is used for radiation (neutron/$$gamma$$ spectrum) measurement in the cell and inquest on the monitoring position of the detector for Pu monitoring. In this paper, we report the result of the dose rate measurement in the cell, improvement of the simulation model which is cleared by comparison between measurement result and calculation result and our future plan.

Journal Articles

Feasibility study of advanced technology for Pu with FP solution monitoring; Overview of research plan and modelling for simulation

Sekine, Megumi; Matsuki, Takuya; Suzuki, Satoshi; Tanigawa, Masafumi; Yasuda, Takeshi; Yamanaka, Atsushi; Tsutagi, Koichi; Nakamura, Hironobu; Tomikawa, Hirofumi; LaFleur, A. M.*; et al.

EUR-28795-EN (Internet), p.788 - 796, 2017/00

The IAEA has proposed in its long-term R&D plan, the development of technology to enable real-time flow measurement of nuclear material as a part of an advanced approach to effective and efficient safeguards for reprocessing facilities. To address this, JAEA has designed and developed a neutron coincidence based nondestructive assay system to monitor Pu directly in solutions which is after purification process and contains very little fission products (FPs). A new detector to enable monitoring of Pu in solutions with numerous FPs is being developed as a joint research program with U.S. DOE at the High Active Liquid Waste (HALW) Storage Facility in Tokai Reprocessing Plant. As the first step, the design information of HALW tank was investigated and samples of HALW was taken and analyzed for Pu concentration and isotope composition, density, content of dominant nuclides emitting $$gamma$$ ray or neutron, etc. in order to develop a Monte Carlo N-Particle Transport Code (MCNP) of the HALW tank. In addition, $$gamma$$ ray source spectra simulated by Particle and Heavy Ion Transport code System (PHITS) was developed by extracting peaks from the analysis data with germanium detector. These outputs are used for the fundamental data in the MCNP model which is then used to evaluate the type of detector, shielding design and measurement positions. In order to evaluate available radiations to measure outside the cell wall, continuous $$gamma$$ ray and neutron measurement were carried out and the results were compared to the simulation results. The measurement results showed that there are no FP peaks above 3 MeV. This paper presents an overview of the research plan, characteristics of HALW, development of source term for MCNP, simulation of radiation dose from the HALW tank and radiation measurement results at outside of cell wall.

Journal Articles

Feasibility study of technology for Pu solution monitoring including FP; Composition research of high active liquid waste and radiation measurement results on the surface of cell

Matsuki, Takuya; Masui, Kenji; Sekine, Megumi; Tanigawa, Masafumi; Yasuda, Takeshi; Tsutagi, Koichi; Ishiyama, Koichi; Nishida, Naoki; Horigome, Kazushi; Mukai, Yasunobu; et al.

Proceedings of INMM 57th Annual Meeting (Internet), 9 Pages, 2016/07

The International Atomic Energy Agency (IAEA) has proposed in its long-term research and development (R&D) plan, development of a real-time measurement technology to monitor and verify nuclear material movement continuously as part of an advanced approach to effectively and efficiently conduct safeguards for reprocessing facilities. Since the Tokai Reprocessing Plant (TRP) has solutions containing both Pu and fission products (FP), a new detector development project to monitor Pu with FP is being carried out from 2015 to 2017. This project is mainly conducted in the High Active Liquid Waste Storage (HALWS) in the TRP. For the first step of this project, as the confirmation of composition of high active liquid waste (HALW) to evaluate neutron/$$gamma$$-ray emitted from solution in the selected HALW tank which has the most amount of Pu in HALW tanks at the TRP, we took HALW sample and conducted $$gamma$$-ray spectrum measurement for HALW. As a study of detector setting location, to survey the available neutron/$$gamma$$-ray (i.e. intensity) at the outside surface of the cell where HALW tank is located, we implemented continuous measurement by neutron/$$gamma$$-ray detector. In this paper, we report three $$gamma$$-ray peaks related with $$^{238}$$Pu and $$^{239}$$Pu measured in the composition research of HALW, which is needed to identify Pu amount by the new detector that we are developing and the result of radiation measurement on the surface of the cell.

Journal Articles

Micromachining of commodity plastics by proton beam writing and fabrication of spatial resolution test-chart for neutron radiography

Sakai, Takuro; Yasuda, Ryo; Iikura, Hiroshi; Nojima, Takehiro; Matsubayashi, Masahito; Kada, Wataru; Koka, Masashi; Sato, Takahiro; Okubo, Takeru; Ishii, Yasuyuki; et al.

Nuclear Instruments and Methods in Physics Research B, 306, p.299 - 301, 2013/07

 Times Cited Count:7 Percentile:49.28(Instruments & Instrumentation)

Oral presentation

Development of spatial evaluation test-chart and high resolution optical system for neutron imaging

Sakai, Takuro; Yasuda, Ryo; Iikura, Hiroshi; Nojima, Takehiro; Matsubayashi, Masahito; Koka, Masashi; Sato, Takahiro; Okubo, Takeru; Ishii, Yasuyuki; Takano, Katsuyoshi*

no journal, , 

Improvement of spatial resolution is one of the most energetic issues on neutron radiography. In this paper, we introduce two novel devices for the imaging technique. One is the spatial evaluation test-chart that is manufactured by using proton scanning microbeam. The finest lines are 3 micron in width. Another is high resolution optical lens for video camera systems. The lens system has 1:1 magnification and the F value of 3. The optical resolution is less than 5 micron.

Oral presentation

Measurement and analysis of radiolytically generated hydrogen from HALW, 1; Measurement and evaluation of the hydrogen concentration in the vessel off-gas

Tomiyama, Masahiro; Yasuda, Takeshi; Tsutagi, Koichi; Yoshino, Yasuyuki; Shirato, Yoji; Nakamura, Yoshinobu; Kinuhata, Hiroshi*; Kodama, Takashi*; Nakano, Masanao*; Tamauchi, Yoshikazu*; et al.

no journal, , 

no abstracts in English

Oral presentation

Measurement and analysis of radiolytically generated hydrogen from HALW, 2; Comparison of measured hydrogen concentration and its estimation

Kinuhata, Hiroshi*; Kodama, Takashi*; Nakano, Masanao*; Tamauchi, Yoshikazu*; Matsuoka, Shingo*; Tomiyama, Masahiro; Yasuda, Takeshi; Tsutagi, Koichi; Yoshino, Yasuyuki; Shirato, Yoji; et al.

no journal, , 

no abstracts in English

Oral presentation

Diffusion of fluorine from fluoride-containing material in decalcified enamel

Matsuda, Yasuhiro*; Okuyama, Katsushi*; Komatsu, Hisanori*; Oki, Saiko*; Hashimoto, Naoki*; Sano, Hidehiko*; Yamamoto, Hiroko*; Iwami, Yukiteru*; Hayashi, Mikako*; Nomachi, Masaharu*; et al.

no journal, , 

no abstracts in English

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, 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.

Oral presentation

Measurement technology and development results for material accountancy in the reprocessing facility

Tanigawa, Masafumi; Matsuki, Takuya; Yasuda, Takeshi; Tsutagi, Koichi; Samoto, Hirotaka; Sekine, Megumi; Suzuki, Satoshi*; Kitao, Takahiko; Nakamura, Hironobu; Isomae, Hidemi

no journal, , 

no abstracts in English

12 (Records 1-12 displayed on this page)
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