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Featured researches published by Toshiaki Hiyama.


Analytica Chimica Acta | 1997

Determination of nitrogen in uranium-plutonium mixed oxide fuel by gas chromatography after fusion in an inert gas atmosphere

Toshiaki Hiyama; Toshio Takahashi; Katsuichiro Kamimura

Abstract A gas chromatographic technique has been developed for the determination of nitrogen in uranium-plutonium mixed oxide fuel after fusion in an inert gas atmosphere. When the sample and pure iron powder in a graphite crucible were heated to approximately 2500 °C by a resistance heating furnace, a large amount of carbon monoxide was evolved with a small amount of nitrogen and hydrogen. A gas chromatograph equipped with a pre-cut system was used for the separation of nitrogen from the carbon monoxide. Nitrogen separated by the gas chromatograph was determined by means of a thermal conductivity detector. Only 100 mg of the sample was used, and the analysis requires about 10 min. No specific skills for glove-box work are necessary. The relative standard deviation and detection limit (3σ-criterion) were less than 5% and 9μg g −1 , respectively. The present method is not only applicable to the analysis of research samples but also to the quality control of uraniumplutonium mixed oxide fuel production lines.


Journal of Nuclear Materials | 1995

Determination of occluded gases in mixed oxide fuel pellets using gas sampling unit and gas chromatography

Toshiaki Hiyama; S. Sugaya; J. Yamamoto; K. Kamimura

Abstract A new technique for the determination of occluded gases in sintered plutonium-uranium mixed oxide (MOX) fuel pellets was developed. The gases extracted from the sample at vacuum condition were injected into a gas chromatograph through an originally developed gas sampling unit. The gases were simultaneously determined using the improved gas chromatograph equipped with several separation columns and a photoionization detector. The relative standard deviations ( n = 10) were 1.0, 3.4, 0.6, 1.0, 1.4, 0.8 and 0.9% for H 2 , O 2 , N 2 , CH 4 , CO 2 , CO and C 2 H 6 , respectively. The gases H 2 , O 2 , N 2 , CH 4 , CO 2 and CO from the MOX fuel pellets were simultaneously determined in this study. The results of gas analysis using this method were in agreement with that of high temperature vacuum extraction method in the range less than 300 μl of extracted gas.


Analytical Sciences | 2008

Spectrophotometric Determination of Plutonium in Highly Radioactive Liquid Waste Using an Internal Standardization Technique with Neodymium(III)

Naoki Surugaya; Shigeo Taguchi; Soichi Sato; Masaru Watahiki; Toshiaki Hiyama


Journal of Radioanalytical and Nuclear Chemistry | 2011

Determination of trace amounts of plutonium in low-active liquid wastes from spent nuclear-fuel reprocessing plants by flow injection-based solid-phase extraction/electrochemical detection system

Shigeo Taguchi; Masahiko Yamamoto; Naoki Surugaya; Akira Kurosawa; Toshiaki Hiyama; Tatsuhiko Tanaka


Analytical Sciences | 2008

Preparation, certification and validation of a stable solid spike of uranium and plutonium coated with a cellulose derivative for the measurement of uranium and plutonium content in dissolved nuclear fuel by isotope dilution mass spectrometry

Naoki Surugaya; Toshiaki Hiyama; A. Verbruggen; R. Wellum


Analytical Sciences | 1996

Determination of Americium in a Nitric Acid Medium Using Second-Order Derivative Spectrophotometry

Toshiaki Hiyama; Shinichi Sugaya; Tomio Kageyama; Katsuichiro Kamimura


Analytical Sciences | 2008

Automated gravimetric sample pretreatment using an industrial robot for the high-precision determination of plutonium by isotope dilution mass spectrometry.

Naoki Surugaya; Toshiaki Hiyama; Masaru Watahiki


Bunseki Kagaku | 2000

Controlled-potential coulometric determination of plutonium in the presence of iron

Toshiaki Hiyama; Tomio Kageyama


International Nuclear Fuel Cycle Conference: Nuclear Energy at a Crossroads, GLOBAL 2013 | 2013

Research and development on waste management for the Fukushima Daiichi NPS by JAEA

Yoshikazu Koma; Takashi Ashida; Yoshihiro Meguro; Yasuaki Miyamoto; Toshiki Sasaki; Isao Yamagishi; Yutaka Kameo; Atsuhiko Terada; Toshiaki Hiyama; Tomozo Koyama; Shuji Kaminishi; Noriyuki Saito; Yasutaka Denda


Bunseki Kagaku | 2010

Determination of trace amounts of uranium by stripping voltammetry using a boron-doped diamond electrode

Shigeo Taguchi; Naoki Surugaya; Akira Kurosawa; Toshiaki Hiyama; Tatsuhiko Tanaka

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Naoki Surugaya

Japan Atomic Energy Agency

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Akira Kurosawa

Japan Atomic Energy Agency

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Shigeo Taguchi

Japan Atomic Energy Agency

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Tatsuhiko Tanaka

Tokyo University of Science

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Masahiko Yamamoto

Japan Atomic Energy Agency

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Masaru Watahiki

Japan Atomic Energy Agency

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Atsuhiko Terada

Japan Atomic Energy Agency

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Isao Yamagishi

Japan Atomic Energy Agency

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J. Yamamoto

Japan Atomic Energy Agency

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K. Kamimura

Japan Atomic Energy Agency

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