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Journal Articles

Investigation of radioactive samples for neutron capture reaction measurements using energy-resolved neutron imaging

Segawa, Mariko; Toh, Yosuke; Kai, Tetsuya; Kimura, Atsushi; Nakamura, Shoji

Annals of Nuclear Energy, 167, p.108828_1 - 108828_5, 2022/03

 Times Cited Count:0 Percentile:0.01(Nuclear Science & Technology)

Journal Articles

Quantitation of trace lanthanide and actinide ions in radioactive samples by capillary electrophoresis-laser-induced fluorescence detection

Haraga, Tomoko; Saito, Shingo*

Bunseki Kagaku, 70(12), p.671 - 679, 2021/12

We developed highly sensitive capillary electrophoresis-laser-induced fluorescence detection methods for lanthanide (Ln) and actinide (An) ions with small sample volume and low emission of waste, by which the radiation risk can be minimized. Specifically, determination of Nd ion in spent nuclear fuel, effective separation between Am and Cm ion, and specific detection of UO$$_{2}$$$$^{2+}$$ in real radioactive samples were achieved by molecular design of fluorescence probes composed of an aminocarboxylate chelating moiety, a fluorophore and a spacer, and unique separation mode based on dynamic ternary complexation. We found that there are appropriate combination of probe and ternary complexation for detection and separation of each Ln and An ions. For example, acyclic and macrocyclic hexadentate is suitable for Ln$$^{3+}$$, Am$$^{3+}$$ and Cm$$^{3+}$$, and planer tetradentate with $$pi$$ electron system is specific for UO$$_{2}$$$$^{2+}$$, with ppt-sub ppt level detection.

JAEA Reports

Automation technique of analytical pre-treatment for radioactive sample measurement using the program written by visual basic for applications

Yamamoto, Masahiko; Karo, Yoshinori*; Kodaka, Noriyasu; Kuno, Takehiko

JAEA-Technology 2019-014, 68 Pages, 2019/10

JAEA-Technology-2019-014.pdf:2.93MB

Analytical devices like syringe pump, electric burette, fraction collector, and electric valve have been controlled by the program written with Visual Basic for Applications (VBA Macro) to automate the column separation of radioactive sample measurement. It is found that VBA Macro can control each device. Therefore, automatic conditioning and separation equipment were made by combining each device and sequentially controlling with the program. The automation conditioning equipment can repeatedly perform conditioning operation with maximum of 8 columns. The automation separation equipment can separate and recover Sr in simulated highly active liquid waste by using Eichrom Technologies Sr resin. It is found that the developed automation method, using commercially available VBA Macro, is effective to reduce labor work, operator's radiation exposure, and to prevent operational error of analysis, together with reducing the cost of automation.

Journal Articles

Construction and performance of a mass spectrometer for radioactive materials

; ; ; *

Shitsuryo Bunseki, 21(1), p.27 - 35, 1973/01

no abstracts in English

Journal Articles

Measurement of radioactive samples

Bunseki Kagaku, 8, P. 897, 1959/00

no abstracts in English

Journal Articles

6.1 Measurement of radioactive samples

Bunseki Kagaku, p.897 - 901, 1959/00

no abstracts in English

Oral presentation

Development of analytical technique for radioactive material using microfludic device

Yamamoto, Masahiko; Kuno, Takehiko; Takamura, Yuzuru*

no journal, , 

Target elements are separated and measured in a glove box (GB) to prevent internal exposure when radioactive material is analyzed. Although liquid-liquid solvent extraction is used for the separation, liquid waste reduction is required due to the organic solvents. Also, an large apparatus such as ICP-OES requires high cost due to the designing sepcific GB for installation. Therefore, small apparatus is desired. In this study, we have been focused on microchemical chip (MCC) and liquid electrode plasma (LEP). Reduction of liquid radioactive waste is expected becuase solvent extraction can be performed in microchannel by using MCC. The emission spectroscopy using LEP (LEP-OES) requires neither plasma gas nor cooling water, and the device is small enough to installed in normal GB. We will report the results of the Pu measurement system combining MCC with liquid scintillation counter, and elemental analysis of liquid radioactive waste by LEP-OES.

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