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Journal Articles

Removal of cesium using cobalt-ferrocyanide-impregnated polymer-chain-grafted fibers

Ishihara, Ryo*; Fujiwara, Kunio*; Harayama, Takato*; Okamura, Yusuke*; Uchiyama, Shoichiro*; Sugiyama, Mai*; Someya, Takaaki*; Amakai, Wataru*; Umino, Satoshi*; Ono, Tsubasa*; et al.

Journal of Nuclear Science and Technology, 48(10), p.1281 - 1284, 2011/10

AA2011-0190.pdf:0.45MB

 Times Cited Count:41 Percentile:95.7(Nuclear Science & Technology)

Journal Articles

Dielectric study on dynamics of electron-beam-induced gelation of hdroxypropylmethylcellulose (HPMC)

Morishita, Satoshi*; Umino, Yuya*; Kita, Rio*; Shinyashiki, Naoki*; Yagihara, Shin*; Furusawa, Kazuya*; Dobashi, Toshiaki*; Nagasawa, Naotsugu

Tokai Daigaku Kiyo Rigakubu, 41, p.105 - 112, 2006/03

Dielectric relaxation measurements were performed for the systems of hydroxypropylmethylcellulose (HPMC) in 1,4-dioxane and HPMC gel immersed in 1,4-dioxane. The HPMC gel was prepared by an electron beam irradiation for HPMC aqueous solution. Two relaxation processes were observed for both samples. Higher frequency process of each sample in the range of 300 kHz - 100 MHz was attributed to a chain motion of HPMC, while lower frequency process observed for the HPMC gel in the range 100 Hz - 300 kHz was significantly larger than the HPMC in dioxane. This observation indicates that DC conductivity due to the beam irradiation had a pronounced effect for the slower relaxation process.

JAEA Reports

Periodic Safety Review of the Experimental Fast Reactor JOYO; Review of Aging Management

Isozaki, Kazunori; Ogawa, Toru; Nishino, Kazunari; Kaito, Yasuaki; Ichige, Satoshi; Sumino, Kozo; Suto, Masayoshi; Kawahara, Hirotaka; Suzuki, Toshiaki; Takamatsu, Misao; et al.

JNC TN9440 2005-003, 708 Pages, 2005/05

JNC-TN9440-2005-003.pdf:31.46MB

Periodic safety review (Review of the aging management) which consisted of Technical review on aging for the safety related structures, systems and components and Establish a long term maintenance program was carried out up to April 2005.1. Technical review on aging for the safety related structures, systems and components It was technically confirmed to prevent the loss of function of the safety related structures, systems and components due to aging phenomena, which (1) irradiation damage, (2) corrosion, (3) abrasion and erosion, (4) thermal aging, (5) creep and fatigue, (6) Stress Corrosion Cracking, (7) insulation deterioration and (8) general deterioration, under the periodic monitoring or renewal of them 2. Establish a long term maintenance program The long term maintenance program during JPY2005 to 2014 were established based on the technical review on aging for the safety related structures, systems and components. It was evaluated that the inspection or renewal based on the long term maintenance program, in addition to the spontaneous inspection long-term schedule of the long term voluntary inspection plan, could prevent the loss of function of the safety related structures, systems and components in future.

Journal Articles

Design and renovation of heat transport system in the experimental fast reactor JOYO

Sumino, Kozo; Ashida, Takashi; Kawahara, Hirotaka; Ichige, Satoshi; Isozaki, Kazunori; Nakai, Satoru

Proceedings of Operating Nuclear Facility Safety(2004ONFS),p204-216, p.204 - 216, 2004/11

None

JAEA Reports

Applicability test of the raman distributed temperature sensor for FBR plant instrumentation

Sumino, Kozo; Ichige, Satoshi; Fukami, Akihiro*; Maeda, Yukimoto; Suzuki, Soju

PNC TN9430 98-008, 40 Pages, 1998/09

PNC-TN9430-98-008.pdf:1.75MB

The Raman Distributed Temperature Sensor (RDTS) based on the Raman Scattering Phenomena in the optical fiber is a system, which can easily measure the accurate temperature distribution. In order to evaluate the applicability of RDTS for FBR plant instrumentation, a temperature distribution measurement using RDTS was performed in the primary cooling system of JOYO. By using two optical fiber sensors, which were installed spirally around the primary piping, the temperature distribution on the primary piping was measured from the 30th through the 32nd duty cycle. In addition, the same test was carried out in the secondary cooling system of JOYO in order to test the measurement data from the primary cooling system. The main results were as follows; (1) The temperature data in the primary cooling system was acquired over 180EFPDs of operation at JOYO (accumulated dose : 3 $$times$$ 10$$^{7}$$ R). (2) The chracteristics of FTR in the high dose rate nuclear plant environment was confirmed. (3) The radiation induced temperature errors were calibrated succesfully by using thermocouple readings. The accuracy of the temperature after calibration was approximately $$pm$$3$$^{circ}$$C. (4) It was confirmed that diffent fiber and insulator settings on the piping cause temperature changes.

Oral presentation

Radiation management for removing of radioactive liquid waste pipeline

Takahashi, Teruhiko; Niinuma, Shinichi; Futagawa, Kazuo; Otsuka, Yoshikazu; Muto, Yasushi; Sakai, Toshiya; Umehara, Takashi; Shimizu, Isamu; Umino, Takaaki; Yamada, Satoshi; et al.

no journal, , 

no abstracts in English

Oral presentation

Development of high-performance adsorptive fibers for decontamination of radioactive substances; Preparation of Sr-adsorptive fibers

Harayama, Takato*; Umino, Satoshi*; Asai, Shiho; Fujiwara, Kunio*; Saito, Kyoichi*; Sugo, Takanobu*

no journal, , 

no abstracts in English

Oral presentation

Study on hydrogen permeation behavior in PyC coated graphite

Suematsu, Senri*; Katayama, Kazunari*; Izumino, Junichi*; Matsuura, Hideaki*; Otsuka, Teppei*; Fukada, Satoshi*; Goto, Minoru; Nakagawa, Shigeaki

no journal, , 

It has been proposed that lithium compounds are loaded into a HTGR and tritium for initial fusion reactors is produced by $$^{6}$$Li(n,$$alpha$$)T reaction. Coating PyC layer on the lithium compounds could be one of the method for preventing the produced tritium leakage. In this study, hydrogen permeation experiment was performed to obtain tritium transmission coefficient in PyC, which is an important value to estimate the amount of the tritium leakage.

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