Field emission-type scanning electron microscope for examination of irradiated fuels

Yasuda, Ryo; Mita, Naoaki; Nishino, Yasuharu; Nakata, Masahito; Nozawa, Yukio; Harada, Katsuya; Kushida, Teruo; Amano, Hidetoshi

Nuclear Technology, 151(3), p.341 - 345, 2005/09

https://doi.org/10.13182/NT05-A3656

The Field Emission type Scanning Electron Microscope (FE-SEM), which is one of effective tools for observation of micr-structures, was installed at the Reactor Fuel Examination Facility (RFEF) in JAERI. The FE-SEM is equipped in a large shield vessel with remote handling systems to keep safety of operators and is modified to enable to manipulate high radioactive materials. The Energy Dispersive Spectrometer (EDS) with radiation-shielded collimators has been also equipped on the FE-SEM to determine element compositions of the observed material samples. Characterization tests were carried out using deposited gold film and Zircaloy cladding tubes with hydrides to confirm the machine performance after the modifications. In the results of the tests, high-resolution images without some noises and fogs were obtained with high magnification above 10,000. Those results show that the FE-SEM keeps the high performance after some improvements and modifications for shielding -rays and handling radioactive samples.

Application of hydrogen analysis by neutron imaging plate method to Zircaloy cladding tubes

Yasuda, Ryo; Nakata, Masahito; Matsubayashi, Masahito; Harada, Katsuya; Hatakeyama, Yuichi; Amano, Hidetoshi

Journal of Nuclear Materials, 320(3), p.223 - 230, 2003/08

https://doi.org/10.1016/S0022-3115(03)00112-0

Neutron radiography is one of effective tools to determine hydrided region in Zircaloy cladding tubes. In this work, the practicability of the neutron radiography for hydrogen analysis is further investigated by using standard samples with known hydrogen concentration. Local hydrogen concentration in hydrided Zircaloy tube is quantitatively estimated using the standard samples by neutron imaging plate (NIP) method. The local area is equivalent to a picture element in the image; e.g., 0.1mm0.1mm. In addition, contribution of an oxide film in the tubes to the images is investigated using oxidized samples with hydrides or no hydride. In NIP images of oxidized tube no oxide film was recognized. Numerical image analysis also shows no effect of the oxide film on the image. These results show that the influence of oxygen on image contrast can be neglected when hydrogen analysis is performed on the Zircaloy tube with oxide film and hydrides by NIP method.

Development of advanced neutron radiography for inspection on irradiated fuels and materials, 3; Examination of neutron imaging plate and computed tomography methods on unirradiated fuel rod

Yasuda, Ryo; Matsubayashi, Masahito; Nakata, Masahito; Harada, Katsuya; Amano, Hidetoshi; Ando, Hitoshi*; Sasajima, Fumio; Nishi, Masahiro; Horiguchi, Yoji

JAERI-Tech 2002-001, 23 Pages, 2002/02

JAERI-Tech-2002-001.pdf:3.79MB

Advanced neutron radiography techniques such as neutron imaging plate (NIP) and Computed Tomography (CT) methods have been investigated the practicality for Post Irradiation Examination (PIE). In this work, an unirradiated fuel rod was examined by NIP and CT methods in order to collect the fundamental data for applying these techniques to PIE.The fuel rod is composed of seven-enriched UO2 pellet and two-natural UO2 pellet that are loaded into a Zircaloy tube. There are somewhat difference in the size and shape among those UO2 pellets. A transmitted and cross-sectional images were obtained by NIP and CT methods, respectively.In the NIP image, the difference in the size, shape, and enrichment among the UO2 pellets is obviously recognized. In the case of CT method, the images clearly show the detailed shape of the cross section in the pellets, in addition, the difference in the enrichment between the natural and enriched pellets is recognized.

PIE(Post Irradiated Examination) techniques for LWR fuel

Amano, Hidetoshi

Saishin Kaku Nenryo Kogaku; Kodoka No Genjo To Tembo, p.261 - 273, 2001/06

no abstracts in English

Development of pellet melting temperature measurement apparatus

Harada, Katsuya; Nishino, Yasuharu; Mita, Naoaki; Amano, Hidetoshi

JAERI-Tech 2000-031, p.27 - 0, 2000/03

JAERI-Tech-2000-031.pdf:2.95MB

no abstracts in English

Density, porosity and grain size, 1; Unirradiated ROX fules

Yanagisawa, Kazuaki; Yamashita, Toshiyuki; Kanazawa, Hiroyuki; Amano, Hidetoshi; Muromura, Tadasumi

Journal of Nuclear Science and Technology, 36(11), p.1052 - 1063, 1999/11

https://doi.org/10.3327/jnst.36.1052

no abstracts in English

Development and application of PIE apparatuses for high-burnup LWR fuels

; Mita, Naoaki; Nishino, Yasuharu; Amano, Hidetoshi

JAERI-Conf 99-009, p.103 - 111, 1999/09

https://jopss.jaea.go.jp/pdfdata/JAERI-Conf-99-009.pdf

no abstracts in English

Current status of PIE techniques in RFEF

Kodaira, Tsuneo; Yamahara, Takeshi; Sukegawa, T.; Nishino, Yasuharu; Kanazawa, Hiroyuki; Amano, Hidetoshi; Nakata, Masahito

HPR-349, 11 Pages, 1998/00

no abstracts in English

Development of post-irradiation examination techniques at the reactor fuel examination facility

Yamahara, Takeshi; Nishino, Yasuharu; Amano, Hidetoshi;

IAEA-TECDOC-822, 0, p.43 - 54, 1995/09

no abstracts in English

Thermal durability of modified synroc material as reactor fuel matrix

; Kanazawa, Hiroyuki; Togashi, Yoshihiro; ; Nishino, Yasuharu; ; Nakata, Masahito; Amano, Hidetoshi;

JAERI-Research 94-008, 20 Pages, 1994/08

JAERI-Research-94-008.pdf:1.8MB

no abstracts in English