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JAEA Reports

Decommissioning of Pre-dismantling Temporary Waste Storage Facility 3 (FPG-03a,b,c) in Plutonium Fuel Production Facility

Shinozaki, Masaru; Aita, Takahiro; Iso, Takahito*; Odakura, Manabu*; Haginoya, Masahiro*; Kadowaki, Hiroyuki*; Kobayashi, Shingo*; Inagawa, Takumu*; Morimoto, Taisei*; Iso, Hidetoshi; et al.

JAEA-Technology 2021-043, 100 Pages, 2022/03

JAEA-Technology-2021-043.pdf:7.49MB

It is planned that the MOX (Mixed Oxide) from the decommissioned facilities in Nuclear Fuel Cycle Engineering Laboratories is going to be consolidated and stored stably and safely for a long term in Plutonium Fuel Production Facility of the Plutonium Fuel Development Center of Nuclear Fuel Cycle Engineering Laboratories. For this purpose, it is necessary to pelletize nuclear fuel materials in the facility and store them in the assembly storage (hereinafter referred to as "waste packaging work") to secure storage space in the plutonium material storage. As a countermeasure to reduce the facility risk in this waste packing work, it was decided to construct a new powder weighing and homogenization mixing facility to physically limit the amount (batch size) of nuclear fuel materials handled at the entrance of the process. In order to secure the installation space for the new facility in the powder preparation room (1) (FP-101), the pre-dismantling temporary waste storage facility 3 (FPG-03a, b, c) was dismantled and removed. This facility consists of a granulating and sizing facility, an additive mixing facility, and a receiving and delivering guided facility, which started to be used from January 1993, and was discontinued on February 3, 2012 and became a waste facility. Subsequently, the dismantling and removal of the interior equipment was carried out by pellet fabrication section for glove operation to reduce the amount of hold-up, and before the main dismantling and removal, there was almost no interior equipment except for large machinery. This report describes the dismantling and removal of the glove box and some interior equipment and peripherals of the facility, as well as the Green House setup method, dismantling and removal procedures, and issues specific to powder process equipment (dust, etc.).

Journal Articles

Development of HCl-free solid phase extraction combined with ICP-MS/MS for rapid assessment of difficult-to-measure radionuclides, 1; Selective measurement of $$^{93}$$Zr and $$^{93}$$Mo in concrete rubble

Do, V. K.; Furuse, Takahiro; Murakami, Erina; Aita, Rena; Ota, Yuki; Sato, Soichi

Journal of Radioanalytical and Nuclear Chemistry, 327(1), p.543 - 553, 2021/01

 Times Cited Count:2 Percentile:72.48(Chemistry, Analytical)

A new HCl-free chromatographic separation procedure has been developed for sequential separation of Zr and Mo from concrete matrices. Accordingly, $$^{93}$$Zr and $$^{93}$$Mo could be sensitively and selectively measured by ICP-MS/MS using ammonia reaction gas. The recoveries of greater than 90% for Zr and Mo from concretes could be achieved. The measurement condition was optimized for complete suppression of interferences from $$^{93}$$Nb and peak tailing from abundant isotopes of Zr and Mo in concrete matrices. The removal of interferences was verified by measurement of radio-contamination-free concretes used as a sample matrix blank. Method detection limits of 1.7 mBq g$$^{-1}$$ and 0.2 Bq g$$^{-1}$$ were achieved for $$^{93}$$Zr and $$^{93}$$Mo, respectively, in the concrete matrices. The interference removal factor for Nb (equivalent to the decontamination factor in radiochemical separation) was of the order of 10$$^{5}$$, and the abundance sensitivity was of the order of 10$$^{-8}$$, indicating that the developed method is reliable for verifying the presence of ultralow concentrations of $$^{93}$$Zr and $$^{93}$$Mo. The present method is suitable for the rapid assessment of $$^{93}$$Zr and $$^{93}$$Mo for radioactivity inventory of concrete rubble.

Journal Articles

Local structure and distribution of remaining elements inside extraction chromatography adsorbents

Watanabe, So; Sano, Yuichi; Shiwaku, Hideaki; Yaita, Tsuyoshi; Ono, Shimpei*; Arai, Tsuyoshi*; Matsuura, Haruaki*; Koka, Masashi*; Sato, Takahiro*

Nuclear Instruments and Methods in Physics Research B, 404, p.202 - 206, 2017/08

 Times Cited Count:3 Percentile:35.6(Instruments & Instrumentation)

Oral presentation

Possibility of direct energy conversion from radiation to electricity using SiC Schottky system

Yoshii, Kenji; Fukuda, Tatsuo; Tanida, Hajime; Shiwaku, Hideaki; Kamiya, Junichiro; Makino, Takahiro*; Yamazaki, Yuichi*; Oshima, Takeshi*; Yaita, Tsuyoshi

no journal, , 

We have carried out direct energy conversion from gamma rays to electricity using SiC free of toxic elements. The experiments were done using synchrotron radiation at the BL22XU beamline. To utilize radioactive wastes as an energy source, the gamma ray energies were 30 and 60 keV, corresponding to the energies from $$^{237}$$Np and $$^{241}$$Am, respectively. Also, CuK$$alpha$$ X-rays were used to show a possibility of micro batteries using radioisotopes. The samples were Ni/SiC Schottky barrier junctions. From dark current experiments, it was found that the samples were regarded as ideal diodes on the basis of the so-called ideality factors. The electric powers under gamma rays and X-rays were found to be about 0.1$$mu$$W, corresponding to efficiencies less than 0.1%. We will also show the results of energy depositions on the basis of Monte Carlo methods.

Oral presentation

Development of plastic enclosure tents for body contamination

Aita, Takahiro; Hirano, Hiroshi*; Kimura, Yasuhisa; Shibanuma, Tomohiro; Yoshida, Masato; Nagai, Yuya; Asakawa, Jun; Shuji, Yoshiyuki

no journal, , 

The newly developed Plastic enclosure tents have reliable airtightness and can be set up in a short time with the small number of persons. Also, in order to prevent the spread of contamination, the exhaust device secures the internal airflow line, and the radiation management device measures the concentration of radioactive materials in the air are in real time. Furthermore, by setting up a multiple of evacuation routes, the decontamination time is shortened even when there are many contaminated persons. Therefore, it is possible to quickly evacuate the contaminated person by having both radiation safety and setting up that can quickly respond to a large-scale body contamination accident.

Oral presentation

Development of simultaneous analytical method for $$^{93}$$Zr and $$^{93}$$Mo based on solid phase extraction combined with ICP-MS/MS, 2; Spectral interference removal for measurement of $$^{93}$$Zr and $$^{93}$$Mo by ICP-MS/MS

Do, V. K.; Furuse, Takahiro; Murakami, Erina; Aita, Rena; Ota, Yuki; Tomitsuka, Tomohiro; Sano, Yuichi; Akimoto, Yuji*; Endo, Tsubasa*; Katayama, Atsushi; et al.

no journal, , 

The paper presents removal of possible interferences including from an isobar ($$^{93}$$Nb) and tailings of adjacent peaks for the quantification of $$^{93}$$Zr and $$^{93}$$Mo using an ICP-MS/MS (Agilent 8900). By using ammonia gas (NH$$_{3}$$) as a reaction gas, $$^{93}$$Zr and $$^{93}$$Mo can be separated from each other and from $$^{93}$$Nb owing to the different reactions of those elements with the reaction gas. Based on the characterization results, we propose a measurement scheme aiming at quantification of $$^{93}$$Zr and $$^{93}$$Mo in environmental samples collected at adjacent location of Fukushima Daiichi Nuclear Power Station.

Oral presentation

Development of simultaneous analytical method for $$^{93}$$Zr and $$^{93}$$Mo based on solid phase extraction combined with ICP-MS/MS, 1; Sequential chemical separation of Zr and Mo from Nb

Furuse, Takahiro; Do, V. K.; Aita, Rena; Ota, Yuki; Murakami, Erina; Tomitsuka, Tomohiro; Sano, Yuichi; Akimoto, Yuji*; Endo, Tsubasa*; Katayama, Atsushi; et al.

no journal, , 

In order to simplify the analysis of $$^{93}$$Zr and $$^{93}$$Mo in radioactive waste from conventional radiation measurement, we have considered analysis method combining solid-phase extraction and ICP-MS/MS. In this presentation, we report the results of a study on sequential chemical separation of Zr and Mo from Nb and sample matrix using ZR resin as a solid-phase extraction resin.

Oral presentation

Acquisition and analysis of alpha-radioactivity data for glove box dismantling

Yoshida, Masato; Kawasaki, Kohei; Aita, Takahiro; Tsubota, Yoichi; Kikuchi, Ryo*; Honda, Fumiya

no journal, , 

no abstracts in English

Oral presentation

Development of dry suction decontamination method for alpha-activity

Asakawa, Jun; Ono, Yosuke; Shibanuma, Tomohiro; Aita, Takahiro; Nagai, Yuya

no journal, , 

no abstracts in English

Oral presentation

Acquisition and analysis of alpha-radioactivity data for glove box dismantling

Yoshida, Masato; Tsubota, Yoichi; Aita, Takahiro

no journal, , 

no abstracts in English

Patent

接続テント及び接続テントの組立方法

平野 宏志; 木村 泰久; 柴沼 智博; 會田 貴洋; 永井 佑哉; 浅川 潤; 吉田 将冬; 周治 愛之

南 明則*

JP, 2019-238397  Patent licensing information

【課題】迅速に組み立て可能な接続テントを提供する。 【解決手段】接続テント(1)は、一対の第1側面フレーム(11、12)及び第1天面フレーム(13)を有する門型フレーム(10)と、第2側面フレーム(21)及び第2天面フレーム(22)を有するL型フレーム(20)と、門型フレーム(10)及びL型フレーム(20)で囲まれた内部空間に収容可能であり、開閉可能な複数の出入口が側面に形成された箱型の部屋テントとを備え、複数の出入口それぞれは、門型フレーム(10)及びL型フレーム(20)の側面に形成された複数の開口のいずれかに対面している。

Patent

ポートキャップ及びグローブボックス

木村 泰久; 平野 宏志; 柴沼 智博; 吉田 将冬; 永井 佑哉; 塙 幸雄; 周治 愛之; 會田 貴洋

南 明則*

JP, 2020-069715  Patent licensing information

【課題】ポート本体とグローブとを間に隙間が生じるのを適切に防止できるポートキャップを提供する。 【解決手段】ポートキャップ(20)は、取付開口(8)から突出する筒体(16)と、先端部が筒体(16)を通じてグローブボックスの内部空間に進入し、基端部が筒体(16)の外周面側に折り返されたグローブ(12)と、折り返されたグローブ(12)と筒体(16)の外周面との間を封止するOリング(13A,13B)及びクランプリング(14)とを備えるグローブポート(10)に取り付けられ、グローブ(12)の内側から筒体(16)に圧入される内筒(21)と、筒体(16)の外側を覆う外筒(22)と、内筒(21)及び外筒(22)の端部同士を接続するフランジ(23)とを備え、内筒(21)の外周面側の先端(21A)は、R面取りされている。

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