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JAEA Reports

Experimental verification of operational conditions for the 3rd glass melter in TVF

Asahi, Yoshimitsu; Fukuda, Shigeki; Shiramizu, Daiki; Miyata, Koshi; Tone, Masaya; Katsuoka, Nanako; Maeda, Yuta; Aoyama, Yusuke; Niitsuma, Koichi; Kobayashi, Hidekazu; et al.

JAEA-Technology 2024-024, 271 Pages, 2025/03

JAEA-Technology-2024-024.pdf:33.98MB
JAEA-Technology-2024-024-hyperlink.zip:31.96MB

A glass melter for the vitrification process of highly active liquid waste in the Tokai Reprocessing Plant, TVF's 3rd melter, was built, and the glass of 18 vitrified waste canisters in weight was melted and poured through a cold test operation. The molten glass surface was covered by a cold cap from feeding fiberglass cartridges saturated with non-radioactive simulant liquid waste as raw material, whose components are equivalent to actual waste. Differences in inherent characteristics of the thermal behavior between the 2nd and the 3rd melter due to the difference in design were considered to establish the procedure to control the new melter. The melter's condition was stabilized at a higher glass temperature and the cooling of 1 kW less in each of the two main electrodes, compared to the 2nd one. Under 39 kW joule heating of the main electrodes with 26 Nm3/h coolant flow rate, it showed the capability to finish heating the bottom furnace in 5 hours before pouring, 2 hours shorter than the 2nd melter. Measurements of the temperature distributions in molten glass and casing surface yielded data that is efficient for developing a simulation model. After Platinum Group Elements (PGE) concentration saturates in the molten glass, feeding raw material and discharging glass were suspended to examine a holding state, indicating PGE settling could retard. During the holding test, observation of the melting process of the cold cap declared that the surface was covered by a thin layer with almost non-fluidity. It will be a reason for choosing the no-slip condition of a fluid calculation, even in the hot-top condition. The investigation of PGE discharging behavior by analyzing the elemental composition of poured glass showed the accumulated PGE amount in the 3rd melter is small compared to the 2nd melter. Inspection of the melter inside after draining out concluded that there were neither significant residual glass nor refractory fragments.

Journal Articles

Ion beam analysis of quaternary Heusler alloy Co$$_{2}$$(Mn$$_{1-x}$$Fe$$_{x}$$)Si(111) epitaxially grown on Ge(111)

Kawakubo, Yuki*; Noguchi, Masaya*; Hirata, Tomoaki*; Narumi, Kazumasa; Sakai, Seiji; Yamada, Shinya*; Hamaya, Kohei*; Miyao, Masanobu*; Maeda, Yoshihito

Physica Status Solidi (C), 10(12), p.1828 - 1831, 2013/12

 Times Cited Count:0 Percentile:0.00(Nanoscience & Nanotechnology)

Journal Articles

RBS study of disordering of Fe$$_{3-x}$$Mn$$_{x}$$Si/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

 Times Cited Count:0 Percentile:0.00(Nanoscience & Nanotechnology)

JAEA Reports

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 500$$^{circ}$$C and 650$$^{circ}$$C 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.

Journal Articles

Thickness and density of additive adsorbed layer on metal surface measured by neutron reflectometry and its effect on tribological properties

Hirayama, Tomoko*; Torii, Takashi*; Konishi, Yohei*; Maeda, Masayuki*; Matsuoka, Takashi*; Inoue, Kazuko*; Hino, Masahiro*; Yamazaki, Dai; Takeda, Masayasu

Nihon Kikai Gakkai Rombunshu, C, 77(779), p.2884 - 2893, 2011/07

Journal Articles

Reduction in degree of absorber-cladding mechanical interaction by shroud tube in control rods for the fast reactor

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

Journal of Nuclear Science and Technology, 48(4), p.580 - 584, 2011/04

One of the challenges in developing a long-life control rod is to restrain absorber-cladding mechanical interaction (ACMI). Its lifetime was limited by ACMI, which is induced by the swelling and relocation of B$$_{4}$$C pellets. To restrain ACMI, a shroud tube was inserted into the gap between the B$$_{4}$$C pellets and the cladding tube. And sodium was selected as bonding material instead of helium to restrain increases in the pellet temperature. As a result of these improvements, the estimated lifetime of the control rod at Joyo was doubled. In this paper, the results of post irradiation examination are reported.

Journal Articles

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

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.

Journal Articles

Investigation of causality in the H-L transition on the JFT-2M tokamak

; ; ; ; ; ; ; Oikawa, Toshihiro; ; ; et al.

Fusion Energy 1996, p.885 - 890, 1997/05

no abstracts in English

Journal Articles

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

Journal Articles

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

JAEA Reports

Design study on H.L.W. geologic repository, IV; for 1984

Ara, Hiroshige*; Fukumitsu, Kenji*; Iizuka, Yunosuke*; Ishii, Takashi*; Izumiya, Yasushi*; Imazu, Masanori*; Utsugida, Yoshizo*; Hasegawa, Makoto*; Maeda, Masaya*; Yabe, Yukio*; et al.

PNC TJ199 84-04VOL1, 20 Pages, 1984/03

PNC-TJ199-84-04VOL1.pdf:0.88MB

None

Oral presentation

Current status of application to meet new regulations and expansion of irradiation capabilities after restart

Saito, Hiroto; Yamamoto, Masaya; Someya, Hiroyuki*; Itagaki, Wataru; Maeda, Shigetaka; Takamatsu, Misao

no journal, , 

Toward restart, the experimental fast reactor Joyo is now under the safety review by regulatory body. After restart, we would like to play a enhanced role of fast neutron irradiation experiments. In order to discuss with irradiation materials researchers, introduce the irradiation capabilities of Joyo after restart.

Oral presentation

Role and current status of existing advanced reactors, 1; Effort of the experimental fast reactor, Joyo

Takamatsu, Misao; Maeda, Shigetaka; Yamamoto, Masaya; Soga, Tomonori; Sekine, Takashi

no journal, , 

no abstracts in English

Oral presentation

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.

Oral presentation

RBS study of disordering of Fe$$_{3-x}$$Mn$$_{x}$$Si/Ge(111) heteroepitaxial interfaces

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

no journal, , 

Oral presentation

Current status of application to meet new regulations and irradiation capabilities after re-start

Yamamoto, Masaya; Saito, Hiroto; Itagaki, Wataru; Maeda, Shigetaka; Takamatsu, Misao

no journal, , 

Joyo is the main fast neutron irradiation facility to develop materials for nuclear industry in Japan. Toward restart, application for relicensing in accordance with newly established regulatory requirements is under discussion. After re-start, we would like to play a enhanced role of fast neutron irradiation experiments. In order to discuss with irradiation materials researchers, introduce the irradiation capabilities of Joyo after re-start.

Oral presentation

None

Naito, Hiroyuki; Yamamoto, Masaya; Itagaki, Wataru; Takeuchi, Tomoaki; Maeda, Shigetaka; Soga, Tomonori

no journal, , 

no abstracts in English

Oral presentation

None

Sasaki, Yuto; Nemoto, Masaya; Maeda, Shigetaka

no journal, , 

no abstracts in English

Oral presentation

The Development of a long life control rod in the fast reactor, 2; Non-destructive PIE results of sodium bonded type control rod irradiated in Joyo

Katsuyama, Kozo; Yamamoto, Masaya; Abe, Kazuyuki; Maeda, Koji; Nagamine, Tsuyoshi; Nakamura, Yasuo

no journal, , 

no abstracts in English

Oral presentation

The Evaluation techniques for irradiation test conditions in Joyo

Itagaki, Wataru; Ito, Chikara; Maeda, Shigetaka; Yamamoto, Masaya

no journal, , 

no abstracts in English

33 (Records 1-20 displayed on this page)