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Journal Articles

Application of FE-SEM to the measurement of U, Pu, Am in the irradiated MA-MOX fuel

Sasaki, Shinji; Tanno, Takashi; Maeda, Koji

Proceedings of 54th Annual Meeting of Hot Laboratories and Remote Handling (HOTLAB 2017) (Internet), 6 Pages, 2017/00

During irradiation in a fast reactor, the microstructure change of the mixed oxide fuels and the changes of element distributions occur because of a radial temperature gradient. Therefore, it is important to study the irradiation behavior of MA-MOX for advancement of fast reactor fuels. In order to make detailed observations of microstructure and elemental analyses of MA-MOX, irradiated MA-MOX specimens were carried out PIE by using a FE-SEM equipped with WDX. Because fuel samples have high radio activities and emit alpha-particles, the instrument was modified. the instrument was installed in a lead shield box and the control unit was separately located outside the box. The microstructure changes were observed in irradiated MA-MOX specimen. The characteristic X-rays peaks were detected successfully. By measuring the intensities of characteristic X-rays, it was tried quantitative analysis of U, Pu, Am along radial direction of irradiated specimen.

Journal Articles

Nondestructive observation of nuclear fuels and materials by using neutron radiography

Yasuda, Ryo; Matsubayashi, Masahito; Nakata, Masahito; Matsue, Hideaki; Nakanishi, Tomoko

Dai-5-Kai Hoshasen Ni Yoru Hihakai Hyoka Shimpojiumu Koen Rombunshu, p.31 - 34, 2005/02

Neutron radiography is an effectively nondestructive tool for inspection of irradiated nuclear fuels and materials. Neutron CT an neutron imaging plate methods, which are advanced techniques in the neutron radiography, enabled to obtain cross-section images and to evaluate an amount of the element compositions. This paper describes results of those methods using unirradiated fuels and materials and discussed the practicability of those methods to irradiated fuels and materials.

JAEA Reports

Annual report on the services for chemical analysis and scientific glassblowing in the fiscal year 2001 and 2002

Ito, Mitsuo; Obara, Kazuhiro; Toida, Yukio*; Suzuki, Daisuke; Gunji, Katsubumi*; Watanabe, Kazuo

JAERI-Review 2004-007, 65 Pages, 2004/03

JAERI-Review-2004-007.pdf:5.53MB

no abstracts in English

JAEA Reports

Nuclear Energy System Department annual report; April 1, 2002 - March 31, 2003

Department of Nuclear Energy System

JAERI-Review 2003-023, 232 Pages, 2003/09

JAERI-Review-2003-023.pdf:16.58MB

The Department has carried out researches and developments (R&Ds) of innovative nuclear energy system and their related fundamental technologies to ensure the long-term energy supply in Japan. The report deals with the R&Ds of an innovative water reactor, called Reduced-Moderation Water Reactor (RMWR), which has the capability of multiple recycling and breeding of plutonium using light water reactor technologies. In addition, as basic studies and fundamental researches of nuclear energy system in general, described are intensive researches in the fields of reactor physics, thermal-hydraulics, nuclear data, nuclear fuels, and materials. These activities are essential not only for the R&Ds of innovative nuclear energy systems but also for the improvement of safety and reliability of current nuclear energy systems. The maintenance and operation of reactor engineering facilities belonging to the Department support experimental activities.

Journal Articles

Effect of neutron irradiation on electromotive force of oxygen sensor using zirconia solid electrolyte

Hiura, Nobuo*; Yamaura, Takayuki; Motohashi, Yoshinobu*; Kobiyama, Mamoru*

Nippon Genshiryoku Gakkai Wabun Rombunshi, 1(2), p.202 - 208, 2002/06

The purpose of this study is to develop oxygen sensor which can measure the oxygen potential of the fuel in a nuclear reactor. The oxygen sensor with CaO stabilized zirconia solid electrolyte has been specially designed in order to prolong its life time. Electromotive force (EMF) of solid galvanic cell Ni/NiO|ZrO2-CaO|Fe/FeO was measured in both the out-pile tests and the in-situ tests using Japan Material Testing Reactor (JMTR), and the characteristics of EMF was discussed. In the out-pile test, it was found that the EMF was almost equal to the theoretical values at temperatures ranging from 700 to 1,000$$^{circ}C$$, and the life span of the sensor was very long up to 980h at 800$$^{circ}C$$. In the in-situ test, it was found that the EMF showed almost the reliable values up to 300 h (neutron fluence (E>1 MeV) 1.5×10$$^{23}$$ m$$^{-2}$$), at temperatures from 700 to 900$$^{circ}C$$. The imprecision of the EMF was found to be within 6% of the theoretical values up to 1,650h irradiation time (neutron fluence (E>1 MeV) 8.0×10$$^{23}$$ m$$^{-2}$$) at 800$$^{circ}C$$. The oxygen sensors were found to be applicable for the oxygen potential measurement of the fuels in a reactor.

Journal Articles

Analysis of nuclear fuels, reactor and environmental materials

Watanabe, Kazuo;

Bunseki, 1993(11), p.883 - 889, 1993/00

no abstracts in English

JAEA Reports

Progress Report of Department ofF Chemistry

JAERI-M 85-213, 378 Pages, 1986/02

JAERI-M-85-213.pdf:9.65MB

no abstracts in English

Oral presentation

Development of laser heating facility for steam oxidation at extreme temperatures

Kurata, Masaki; Pham, V. H.; Nagae, Yuji

no journal, , 

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