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Journal Articles

Spectrochemistry of technetium by liquid electrode plasma optical emission spectrometry and its applicability of quantification for highly active liquid waste

Yamamoto, Masahiko; Do, V. K.; Taguchi, Shigeo; Kuno, Takehiko; Takamura, Yuzuru*

Spectrochimica Acta, Part B, 155, p.134 - 140, 2019/05

 Times Cited Count:5 Percentile:57.68(Spectroscopy)

The emission spectra of technetium (Tc) by liquid electrode plasma optical emission spectrometry have been investigated in this study. From the spectra, 52 emission peaks of Tc were observed in the 250-500 nm wavelength range. All peaks were assigned to the neutral state or singly ionized state. The relative intensities of these peaks were similar to those excited by an electric spark. The strongest intensity peaks were found at 254.3 nm, 261.0 nm, and 264.7 nm. Spectral interferences of coexisting elements in highly active liquid waste of reprocessing stream on those three strongest peaks were investigated using simulated sample. No spectral interferences were observed around the 264.7 nm Tc peak. Therefore, analytical performance using 264.7 nm peak was evaluated. The detection limit, estimated on standard and blank samples in 0.4 M nitric acid, was 1.9 mg/L. The relative standard deviation of Tc standard sample (12.0 mg/L) was 3.8% (N = 5, 1$$sigma$$).

Journal Articles

Electron-tracking Compton camera imaging of technetium-95m

Hatsukawa, Yuichi*; Hayakawa, Takehito*; Tsukada, Kazuaki; Hashimoto, Kazuyuki*; Sato, Tetsuya; Asai, Masato; Toyoshima, Atsushi; Tanimori, Toru*; Sonoda, Shinya*; Kabuki, Shigeto*; et al.

PLOS ONE (Internet), 13(12), p.e0208909_1 - e0208909_12, 2018/12

 Times Cited Count:0 Percentile:0.01(Multidisciplinary Sciences)

Imaging of $$^{95m}$$Tc radioisotope was conducted using an electron tracking-Compton camera (ETCC). $$^{95m}$$Tc emits 204, 582, and 835 keV $$gamma$$ rays, and was produced in the $$^{95}$$Mo(p,n)$$^{95m}$$Tc reaction with a $$^{95}$$Mo-enriched target. The recycling of the $$^{95}$$Mo-enriched molybdenum trioxide was investigated, and the recycled yield of $$^{95}$$Mo was achieved to be 70% - 90%. The images were obtained with each of the three $$gamma$$ rays. Results showed that the spatial resolution increases with increasing $$gamma$$-ray energy, and suggested that the ETCC with high-energy $$gamma$$-ray emitters such as $$^{95m}$$Tc is useful for the medical imaging of deep tissue and organs in the human body.

Journal Articles

Study on electrolytic reduction of pertechnetate in nitric acid solution for electrolytic extraction of rare metals for future reprocessing

Asakura, Toshihide; Kim, S.-Y.; Morita, Yasuji; Ozawa, Masaki*

Journal of Nuclear and Radiochemical Sciences, 6(3), p.267 - 269, 2005/12

An electrolytic extraction (EE) method, i.e. electro-reductive deposition, of Tc from nitric acid aqueous solution was studied for future reprocessing. After 30 min of constant potential electrolysis by carbon electrode at -0.3 V vs. SSE (Standard Silver Electrode), Tc concentration in 3 M nitric acid decreased to 93 % of the initial value, which corresponds to 7 % of deposition. With co-existence of Pd, the value reached to 15 % of deposition equivalent by electrolysis at $$pm$$0.0 V vs. SSE for 60 min. An acceleration effect of Pd on Tc deposition (promoter effect) was suggested. The concentration, however, increased to the initial value after further electrolysis and competing re-dissolution of deposited Tc was also suggested. In cyclic voltammetry measurements, it was found that the deposit from Tc-Pd-Ru-Rh solution dissolved easier than that from Pd-Ru-Rh did. In electrolyzed Tc solution, an absorption peak at 482 nm was found. It can be attributed to the complex with nitrite anion, and the complex formation is proposed as one possible mechanism of Tc re-dissolution.

Journal Articles

Technetium separation for future reprocessing

Asakura, Toshihide; Hotoku, Shinobu; Ban, Yasutoshi; Matsumura, Masakazu; Morita, Yasuji

Journal of Nuclear and Radiochemical Sciences, 6(3), p.271 - 274, 2005/12

Tc extraction and separation experiments were performed basing on PUREX technique with using spent UO$$_{2}$$ fuel with burn-up of 44 GWd/t. The experimental results were examined with performing calculations by a simulation code ESSCAR (Extraction System Simulation Code for Advanced Reprocessing). It was demonstrated that Tc can be almost quantitatively extracted from a dissolver solution and that Tc can also be almost quantitatively recovered by scrubbing. Further, it was clearly presented from the calculation results of ESSCAR that the extraction mechanism of Tc is dominated by the synergistic effect of Zr and U.

Journal Articles

Research committee on Ruthenium and Technetium Chemistry in PUREX System, Organized by the Atomic Energy Society of Japan

Matsumoto, Shiro*; Uchiyama, Gunzo; Ozawa, Masaki*; Kobayashi, Y.*; Shirato, K.*

Radiochemistry, 45(3), p.219 - 224, 2003/05

no abstracts in English

Journal Articles

Fundamental properties of targets for transmutation of technetium-99 and iodine-129

Minato, Kazuo; Shirasu, Yoshiro; Nishihara, Kenji

Proceedings of International Conference on Back-End of the Fuel Cycle: From Research to Solutions (GLOBAL 2001) (CD-ROM), 8 Pages, 2001/09

The concept of transmutations of Tc-99 and I-129 to stable nuclides is an attractive option to reduce the long-term risk of the storage of high-level waste from nuclear reactors. For the target for transmutation of Tc-99, the thermal expansions and heat capacities of Tc-Ru alloys were measured to build a database of the Tc metal target. For the target for transmutation of I-129, literature survey and experimental studies on characterization and fabrication of targets were made to select suitable chemical forms for the target. In the literature survey, chemical forms of iodide, iodate and iodide oxide were considered.

Journal Articles

Targets for LIFP transmutation

Minato, Kazuo

Nihon Genshiryoku Gakkai 'Kodo Nenryo Gijutsu' Kenkyu Senmon Iinkai Hokokusho, No.115, p.481 - 486, 2001/06

no abstracts in English

Journal Articles

PARC process for an advanced PUREX process

Uchiyama, Gunzo; Mineo, Hideaki; Hotoku, Shinobu; Asakura, Toshihide; Kamei, Kazushige; Watanabe, Makio; Nakano, Yuji*; Kimura, Shigeru; Fujine, Sachio

Progress in Nuclear Energy, 37(1-4), p.151 - 156, 2000/12

 Times Cited Count:7 Percentile:48.29(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Characterization of technetium-ruthenium alloys for transmutation of technetium metal

Shirasu, Yoshiro; Minato, Kazuo

Proc. of the Int. Conf. on Future Nuclear Systems (GLOBAL'99)(CD-ROM), 7 Pages, 1999/00

no abstracts in English

Journal Articles

Properties of technetium and technetium-ruthenium alloys for transmutation of technetium

Minato, Kazuo; Shirasu, Yoshiro

Proceedings of 2nd Japanese-Russian Seminar on Technetium, p.77 - 78, 1999/00

no abstracts in English

Journal Articles

Management of neptunium and technetium in an advanced PUREX process

Uchiyama, Gunzo; Hotoku, Shinobu; Watanabe, Makio; Kamei, Kazushige; Mineo, Hideaki; Nakano, Yuji*; Kimura, Shigeru; Asakura, Toshihide; Fujine, Sachio

Proceedings of 7th International Conference on Radioactive Waste Management and Environmental Remediation (ICEM '99) (CD-ROM), p.5 - 0, 1999/00

no abstracts in English

Journal Articles

Thermal conductivity of technetium

Minato, Kazuo; Serizawa, Hiroyuki; Fukuda, Kosaku

Journal of Alloys and Compounds, 267, p.274 - 278, 1998/00

 Times Cited Count:6 Percentile:48.07

no abstracts in English

Journal Articles

Preparation and characterisation of technetium metal and technetium-ruthenium alloys

Minato, Kazuo; Shirasu, Yoshiro

Proc. of 5th Int. Information Exchange Meeting on Actinide and Fission Product Partitioning, p.223 - 230, 1998/00

no abstracts in English

Journal Articles

The Separation of neptunium and technetium in an advanced Purex process

Uchiyama, Gunzo; Asakura, Toshihide; Hotoku, Shinobu; Fujine, Sachio

Solvent Extr. Ion Exch., 16(5), p.1191 - 1213, 1998/00

no abstracts in English

Journal Articles

The Separation of neptunium and technetium in an advanced purex process

Uchiyama, Gunzo; Asakura, Toshihide; Hotoku, Shinobu; Fujine, Sachio

Solvent Extr. Ion Exch., 16(5), p.1191 - 1213, 1998/00

 Times Cited Count:11 Percentile:53.18(Chemistry, Multidisciplinary)

no abstracts in English

JAEA Reports

Sample preparation and characterization of technetium metal

Minato, Kazuo; Serizawa, Hiroyuki; Fukuda, Kosaku; Ito, Mitsuo

JAERI-Research 97-077, 17 Pages, 1997/10

JAERI-Research-97-077.pdf:1.09MB

no abstracts in English

Journal Articles

A New separation process of neptunium, technetium, plutonium and uranium using butyraldehydes as reductants in nuclear fuel reprocessing

Uchiyama, Gunzo; Asakura, Toshihide; ; Fujine, Sachio; Maeda, Mitsuru

Value Adding Through Solvent Extraction (Proc. of ISEC 96), 2, p.1291 - 1296, 1996/00

no abstracts in English

JAEA Reports

Measurement of technetium emission lines by inductively coupled plasma emission spectrometry

Watanabe, Kazuo;

JAERI-Research 95-066, 49 Pages, 1995/10

JAERI-Research-95-066.pdf:0.98MB

no abstracts in English

Journal Articles

Simulation of technetium behaviour in Purex extraction system

Fujine, Sachio; Tachimori, Shoichi; ; Suzuki, Shinichi; Maeda, Mitsuru; *; *

Proceedings of 4th International Conference on Nuclear Fuel Reprocessing and Waste Management; RECOD '94, Vol.1, 0, 14 Pages, 1994/00

no abstracts in English

Journal Articles

Distribution coefficient measurements of Tc,Np(IV) and Np(VI) between nitric acid solutions containing U and Pu and 30% TBP/n-dodecane

Fujine, Sachio; Uchiyama, Gunzo; Maeda, Mitsuru; R.Thompson*; C.Mason*; R.Bush*

Solvent Extraction in the Process Industries, Vol. 3, p.1789 - 1796, 1993/00

no abstracts in English

24 (Records 1-20 displayed on this page)