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Journal Articles

Temperature effects on local structure, phase transformation, and mechanical properties of calcium silicate hydrates

Im, S.*; Jee, H.*; Suh, H.*; Kanematsu, Manabu*; Morooka, Satoshi; Koyama, Taku*; Nishio, Yuhei*; Machida, Akihiko*; Kim, J.*; Bae, S.*

Journal of the American Ceramic Society, 104(9), p.4803 - 4818, 2021/09

 Times Cited Count:4 Percentile:67.14(Materials Science, Ceramics)

Journal Articles

Heat treatment of phosphate-modified cementitious matrices for safe storage of secondary radioactive aqueous wastes in Fukushima Daiichi Nuclear Power Plant

Irisawa, Keita; Taniguchi, Takumi; Namiki, Masahiro; Garc$'i$a-Lodeiro, I.*; Osugi, Takeshi; Sakakibara, Tetsuro; Nakazawa, Osamu; Meguro, Yoshihiro; Kinoshita, Hajime*

Proceedings of 2017 International Congress on Advances in Nuclear Power Plants (ICAPP 2017) (CD-ROM), 6 Pages, 2017/04

A solidification technique with minimized water content is being developed using phosphate cements for the safe storage of secondary radioactive wastes in the Fukushima Daiichi Nuclear Power Plant. Conventional cement systems become solidified via hydration reactions, and need a certain water content. Phosphate cement systems, however, become solidified via an acid-base reaction, and so they only require water mainly for reasons of workability. A reduced water content of phosphate cement systems is beneficial for the immobilization of the radioactive wastes from mitigating the potential to generate hydrogen gas by the radiolysis of water by radioactive wastes. The current study investigated the water content and mineralogy of calcium aluminate cement (CAC) and phosphate-modified CAC (CAP) cured in open systems at 60, 90 and 120 $$^{circ}$$C and in a closed system at 20 $$^{circ}$$C as a reference case. Water contents in both the CAC and the CAP were seen to decrease as curing progressed. For $$geq$$ 90 $$^{circ}$$C, the CAP contained less water than CAC. Free water in CAC converted to structural water by heat treatment, but this was not the case for CAP. An orthophosphate hydrate salt, a precursor phase of hydroxyapatite, was found in CAP when cured at 20 and 60 $$^{circ}$$C, and a mixture of the orthophosphate hydrate salt and hydroxyapatite, Ca$$_{10}$$(PO$$_{4}$$)$$_{6}$$(OH)$$_{2}$$, were formed in the CAP when cured at 90 $$^{circ}$$C. Phosphate products in CAP cured at 120 $$^{circ}$$C appears to consist of a different phosphate phase compared with the CAP cured at 20, 60 and 90 $$^{circ}$$C.

Journal Articles

Key achievements in elementary R&D on water-cooled solid breeder blanket for ITER test blanket module in JAERI

Suzuki, Satoshi; Enoeda, Mikio; Hatano, Toshihisa; Hirose, Takanori; Hayashi, Kimio; Tanigawa, Hisashi; Ochiai, Kentaro; Nishitani, Takeo; Tobita, Kenji; Akiba, Masato

Nuclear Fusion, 46(2), p.285 - 290, 2006/02

 Times Cited Count:2 Percentile:7.41(Physics, Fluids & Plasmas)

This paper presents significant progress in R&D of key technologies on the water-cooled solid breeder blanket for the ITER-TBM in JAERI. By the improvement of heat treatment process for blanket module fabrication, a fine-grained microstructure of F82H, can be obtained by homogenizing it at 1150 $$^{circ}$$C followed by normalizing at 930 $$^{circ}$$C after the HIP process. Moreover, a promising bonding process for a tungsten armor and an F82H structural material was developed by using a uniaxial hot compression without any artificial compliant layer. Also, it has been confirmed that a fatigue lifetime correlation, which was developed for ITER divertor, can be applicable for F82H first wall mock-up. As for R&D on a breeder material, Li$$_{2}$$TiO$$_{3}$$, the effect of compression loads on thermal conductivity of pebble beds has been clarified. JAERI have extensively developed key technologies for ITER-TBM, and now steps up into an engineering R&D stage, where integrated performance of TBM structures will be demonstrated by scalable mock-ups.

Journal Articles

Improved cavitation resistance of structural materials in pulsed liquid metal targets by surface hardening

Koppitz, T.*; Jung, P.*; M$"u$ller, G.*; Weisenburger, A.*; Futakawa, Masatoshi; Ikeda, Yujiro

Journal of Nuclear Materials, 343(1-3), p.92 - 100, 2005/08

 Times Cited Count:7 Percentile:46.25(Materials Science, Multidisciplinary)

Cavitation damage of structural materials due to pressure waves is expected to be one of the majior life-time limiting factors in high power liquid metal spallation targets under pulsed operation. Two methods are developed for the European Spallation Source (ESS) to mitigate this damage: Introduction of gas bubbles to surpress the pressure pulse and surface-hardening of structural materials. Surface-hardening of four 8-13%Cr martenstic steels was examined by thermal treatment with pulsed or scanned electron- and laser-beams as well as by nitriding in plasma. A specimens of the 12%Cr steel were tested in liquid mercury under pulsed proton irradiation, and under mechanical pulsed-loading. Surface damage was analysed by optical, confocal-laser, or scanning-electron microscopy, showing in both tests much better resistance of the hardened material compared to standard condition.

Journal Articles

Effects of helium production and heat treatment on neutron irradiation hardening of F82H steels irradiated with neutrons

Wakai, Eiichi; Taguchi, Tomitsugu; Yamamoto, Toshio*; Tomita, Hideki*; Takada, Fumiki; Jitsukawa, Shiro

Materials Transactions, 46(3), p.481 - 486, 2005/03

 Times Cited Count:7 Percentile:52.75(Materials Science, Multidisciplinary)

no abstracts in English

JAEA Reports

Development of the fabrication technology for the superconducting coils in the ITER magnet system and its achievements

Hamada, Kazuya; Nakajima, Hideo; Okuno, Kiyoshi; Endo, Sakaru*; Kikuchi, Kenichi*; Kubo, Yoshio*; Aoki, Nobuo*; Yamada, Yuichi*; Osaki, Osamu*; Sasaki, Takashi*; et al.

JAERI-Tech 2002-027, 23 Pages, 2002/03

JAERI-Tech-2002-027.pdf:2.94MB

The Engineering Design Activities (EDA) for the International Thermonuclear Experimental Reactor (ITER) was performed under the collaboration of Japan, EU, Russia and the US. The EDA was successfully completed in July 2001, in which the development of fabrication technology for advanced components, such as superconducting coils, was conducted. The ITER magnet system consists of Toroidal Field coils, a Central Solenoid (CS), Poloidal Field coils and Correction coils. The construction of these coils requires advanced technologies that fairly exceeded those available at the start of the EDA. Therefore, CS Model Coil and TF Model Coil projects were implemented. To fabricate the CS Model Coil, the fabrication technologies for high performance strand, large cable, winding, heat treatment, joint and insulation are indispensable. This report describes the above detailed fabrication technologies successfully developed in the CS Model Coil Project.

Journal Articles

R&D activity of SAGBO avoidance for the CS insert fabrication

Sugimoto, Makoto; Isono, Takaaki; Koizumi, Norikiyo; Nakajima, Hideo; Kato, Takashi; Hamada, Kazuya; Nunoya, Yoshihiko; Matsui, Kunihiro; Sawada, Kenji*; Takahashi, Yoshikazu; et al.

IEEE Transactions on Applied Superconductivity, 9(2), p.636 - 639, 1999/06

 Times Cited Count:1 Percentile:17.33(Engineering, Electrical & Electronic)

no abstracts in English

Journal Articles

Heat treatment effect on bilayer silica scale formed on Si-SiC

Futakawa, Masatoshi; Steinbrech, R. W.*; Wakui, Takashi*; *

Hyomen Gijutsu, 50(1), p.58 - 62, 1999/00

no abstracts in English

Journal Articles

Development of high strength austenitic stainless steel for conduit of Nb$$_{3}$$Al conductor

Nakajima, Hideo; Nunoya, Yoshihiko; O.Ivano*; Ando, Toshinari; Kawasaki, T.*; Hanawa, Hiromi*; Seki, Shuichi*; Takano, Katsutoshi*; Tsuji, Hiroshi; *; et al.

Advances in Cryogenic Engineering Materials, Vol.42, p.323 - 330, 1996/00

no abstracts in English

Journal Articles

Effect of sensitizing heat treatment on fatigue crack growth properties at liquid helium temperature

*; *; O.Ivano*; Nunoya, Yoshihiko; Nakajima, Hideo; Tsuji, Hiroshi

Fatigue & Fracture of Engineering Materials & Structures, 18(6), p.671 - 678, 1995/00

 Times Cited Count:1 Percentile:19.54(Engineering, Mechanical)

no abstracts in English

JAEA Reports

Measurement of Secondary Electron Emission Coefficient of Wall Materials Using Auger Electron Spectroscopy

Hiroki, S.; ; *; ; Murakami, Yoshio

JAERI-M 85-123, 23 Pages, 1985/08

JAERI-M-85-123.pdf:0.71MB

no abstracts in English

Journal Articles

The Effect of heat treatment on density and structure of SiC

; Ikawa, Katsuichi; Iwamoto, K.

Journal of Nuclear Materials, 92(2), p.351 - 353, 1980/00

 Times Cited Count:20 Percentile:97.17(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Heat treatment and isothermal crystallization of as-polymerized polytetrafluoroethylene

; Takehisa, Masaaki; Machi, Sueo

Reports on Progress in Polymer Physics in Japan, 17, p.217 - 220, 1974/00

no abstracts in English

Journal Articles

Effect of heat treatment for the distribution of boron in incoloy-800 alloy

;

Journal of Nuclear Materials, 45(1), p.82 - 86, 1972/01

 Times Cited Count:1

no abstracts in English

Journal Articles

Oxidation of UO$$_{2}$$ pellet in air; Effect of heat-treatment of pellet on particle size distribution of powders produced

; ; ;

Journal of Nuclear Science and Technology, 5(12), p.652 - 653, 1968/00

 Times Cited Count:14

no abstracts in English

Journal Articles

Effects of ionizing radiation of polyvinyl alcohol, 2; Changes of physical properties of the irradiated specimen caused by heat treatment

Journal of the Physical Society of Japan, 13, P. 614, 1958/00

no abstracts in English

17 (Records 1-17 displayed on this page)
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