RBS study of disordering of FeMnSi/Ge(111) heteroepitaxial interfaces

Noguchi, Masaya*; Hirata, Tomoaki*; Kawakubo, Yuki*; Narumi, Kazumasa; Sakai, Seiji; Maeda, Yoshihito

Physica Status Solidi (C), 10(12), p.1732 - 1734, 2013/12

https://doi.org/10.1002/pssc.201300380

Compatibility of zirconium alloys in high-temperature sodium

Furukawa, Tomohiro; Kato, Shoichi; Maeda, Shigetaka; Yamamoto, Masaya; Sekine, Takashi; Ito, Chikara

JAEA-Research 2011-039, 20 Pages, 2012/02

JAEA-Research-2011-039.pdf:3.4MB

Application of zirconium alloy as a neutron reflector around the driver fuel region of the Japanese experimental fast reactor JOYO has been planned for a further increase of core average burn-up. In order to investigate the compatibility of the zirconium alloys with high-temperature sodium which is coolant of the JOYO, corrosion test in sodium and tensile test of the exposed alloys were performed. The corrosion test was done at 500C and 650C in stagnant/flowing sodium for two kinds of zirconium alloys, and then weight change measurement and metallurgical observation were carried out. The tensile test was performed in air at the same temperature with the sodium exposure.

Core modification to improve irradiation efficiency of the experimental fast reactor Joyo

Maeda, Shigetaka; Yamamoto, Masaya; Soga, Tomonori; Sekine, Takashi; Aoyama, Takafumi

Journal of Nuclear Science and Technology, 48(4), p.693 - 700, 2011/04

https://doi.org/10.3327/jnst.48.693

Core modification was investigated to further increase the core burn-up of the experimental fast reactor Joyo. This modification also enables the core to accommodate more irradiation test subassemblies that have lower fissile material content compared to the driver fuel. The design calculations showed that the replacement of the radial reflector elements made of stainless steel with those made of zirconium of nickel-base ally is effective in improving neutron efficiency. The irradiation tests capacity can be increased by reducing the number of control rods based on the re-evaluation of the design margin in the control rod worth calculation. These modifications will be useful to save driver fuels and to enhance the Joyo's irradiation capability.

Divertor biasing effects to reduce L/H power threshold in the JFT-2M tokamak

Miura, Yukitoshi; *; *; Hoshino, Katsumichi; *; *; Kasai, Satoshi; Kawakami, Tomohide; Kawashima, Hisato; Maeda, M.*; et al.

Fusion Energy 1996, p.167 - 175, 1997/05

no abstracts in English

ELM control and boundary plasma modification in the JFT-2M tokamak

Tamai, Hiroshi; Shoji, Teruaki; Miura, Yukitoshi; Nagashima, Keisuke; Kawashima, Hisato; Matsuda, Toshiaki; Ogawa, Hiroaki; Maeno, Masaki; Yamauchi, Toshihiko; Uehara, Kazuya; et al.

IAEA-CN-60/A1-7, 0, p.137 - 144, 1995/00

no abstracts in English

Development of hydride neutron absorber for fast reactor, 8; Preparation and implementation of the irradiation test in Experimental Fast Reactor Joyo

Ito, Kazuhiro; Yamamoto, Masaya; Maeda, Koji; Akasaka, Naoaki; Harada, Akio; Konashi, Kenji*

no journal, , 

As part of "Development of Hydride Neutron Absorber for Fast Reactor", a series of neutron irradiation experiment with in HfH, (Gd+ZR)H and stainless steel specimens was performed in experimental fast reactor Joyo. Here, the stainless steel specimens were coated by oxide film to simulate a cladding tube. In this report, the irradiation examination plan and a result were summarized.

Development of long-lived control rods for the fast reactor

Donomae, Takako; Katsuyama, Kozo; Tachi, Yoshiaki; Maeda, Koji; Yamamoto, Masaya; Soga, Tomonori

no journal, , 

Sodium bonded control rods for fast reactors have been developed in Japan. Their irradiation test was done in the experimental fast reactor Joyo. The control rods were irradiated at 10010 cap/cm for the maximum burn up of the boron carbide (B C) pellets. To control against absorber-cladding mechanical interaction (ACMI), a shroud tube was inserted between the B C pellet stack and cladding. The inside of the control rod pins was filled with sodium. After irradiation, there was no remarkable change in the integrity of the cladding tubes. On the other hand, some cracks were found on the shroud tube at the high burn-up region of B C pellets. It was concluded from these results that if cracks of shroud tubes occurred, there was almost no diameter increase of the cladding tube. So the B C pellet relocation was safely restrained by the shroud tube and the cladding tube at an irradiation of 10010 cap/cm.

Probabilistic safety assessment on the experimental fast reactor Joyo, 4-1; Identification of the most important accident sequence on risk assessment of Joyo

Yamamoto, Masaya; Kawahara, Hirotaka; Terakado, Tsuguo; Maeda, Shigetaka; Saito, Hiroto; Aoyama, Takafumi

no journal, , 

Frequency of ATWS (Anticipated Transient Without Scram) and PLOHS(Protected Loss of Heat Sink) are relatively high in Joyo. To identificate the most important accident and to select the subject of Joyo's level 2 PSA (Probabilistic Safety Assessment), frequency of these accidents were estimated through dynamics characteristic analysis and natural circulation analysis with detailed success standard. Moreover, consequence of these accidents were also evaluated. As a results of these evaluation, the most important accident is identified as UTOP and this accident is selected to the subject of Joyo's level 2 PSA.

RBS study of disordering of FeMnSi/Ge(111) heteroepitaxial interfaces

Noguchi, Masaya*; Hirata, Tomoaki*; Kawakubo, Yuki*; Narumi, Kazumasa; Sakai, Seiji; Maeda, Yoshihito

no journal, , 

Evaluation of interfaces of FeSi epitaxially grown on Si(111) with ion channeling

Kawakubo, Yuki*; Noguchi, Masaya*; Hirata, Tomoaki*; Maeda, Yoshihito; Sakai, Seiji; Narumi, Kazumasa

no journal, , 

no abstracts in English