Simultaneous analysis of silicon and boron dissolved in water by combination of electrodialytic salt removal and ion-exclusion chromatography with corona charged aerosol detection

Mori, Masanobu*; Sagara, Katsuya*; Arai, Kaori*; Nakatani, Nobutake*; Ohira, Shinichi*; Toda, Kei*; Itabashi, Hideyuki*; Kozaki, Daisuke*; Sugo, Yumi; Watanabe, Shigeki; et al.

Journal of Chromatography A, 1431, p.131 - 137, 2016/01

https://doi.org/10.1016/j.chroma.2015.12.064

Study on engineering technologies in the Mizunami Underground Research Laboratory; FY2012 (Contract research)

Fukaya, Masaaki*; Noda, Masaru*; Hata, Koji*; Takeda, Yoshinori*; Akiyoshi, Kenji*; Ishizeki, Yoshikazu*; Kaneda, Tsutomu*; Sato, Shin*; Shibata, Chihoko*; Ueda, Tadashi*; et al.

JAEA-Technology 2014-019, 495 Pages, 2014/08

JAEA-Technology-2014-019.pdf:82.23MB

The researches on engineering technology in the Mizunami Underground Research Laboratory (MIU) plan consists of (1) research on engineering technology deep underground, and (2) research on engineering technology as a basis of geological disposal. The former research is mainly aimed in this study, which is categorized in (a) development of design and construction planning technologies, (b) development of construction technologies, (c) development of countermeasure technologies, and (d) development of technologies for security. In this study, the researches on engineering technology are being conducted in these four categories by using data measured during construction as a part of the second phase of the MIU plan.

Metamagnetic behavior in heavy-fermion compound YbIrZn

Takeuchi, Tetsuya*; Yasui, Shinichi*; Toda, Masatoshi*; Matsushita, Masaki*; Yoshiuchi, Shingo*; Oya, Masahiro*; Katayama, Keisuke*; Hirose, Yusuke*; Yoshitani, Naohisa*; Honda, Fuminori*; et al.

Journal of the Physical Society of Japan, 79(6), p.064609_1 - 064609_15, 2010/06

https://doi.org/10.1143/JPSJ.79.064609

Development of a slim manipulator type fuel handling machine for a commercialized fast reactor

Chikazawa, Yoshitaka; Usui, Shinichi; Konomura, Mamoru; Sadahiro, Daisuke*; Tozawa, Katsuhiro*; Hori, Toru*; Toda, Mikio*; Kotake, Shoji*

Proceedings of 14th International Conference on Nuclear Engineering (ICONE-14) (CD-ROM), 7 Pages, 2006/07

A seismic analysis has been performed showing that the seismic interaction between the UIS and the FHM can be avoided adopting gapless bearings at the FHM arm joint. An angular contact ball bearing is suitable for the new FHM since it can eliminate gaps by preload pressure. A major problem of the FHM bearings is lubrication since the contact pressure between steel rings and ball increases because of ball bearing. Additionally, FHM operating temperature is about 200 deg-C and normal grease is not applicable under argon gas with sodium vapor. A endurance test with 1/10 scale bearings in the air has been performed to show applicability of angular contact ball bearings to the FHM arm joint. The results with 20,000 cycle showed that bearings with combination of MoS coating steel rings and ceramics balls can be tolerable as the FHM operating condition. A real scale bearing test in argon gas with sodium vapor has also been demonstrated to reveal bearing size and sodium vapor effects.

Scattering Profiles of Sparks and Combustibility of Filter against Hot Sparks

Asazuma, Shinichiro; Okada, Takashi; Kashiro, Kashio; Matsumoto, Masaki; Nakata, Keiji*; Gonnokami, Kiyomi*; Toda, Rikiya*

JNC TN8430 2003-011, 56 Pages, 2004/01

JNC-TN8430-2003-011.pdf:2.07MB

The glove-box dismantling facility in the Plutonium Fuel Production Facility is developed to dismantle after-service glove-boxes with remote-controlled devices such as an arm-type manipulator. An abrasive wheel cutter, which is used to size reduce the gloveboxes, generates sparks during operation. This dispersing spark was a problem from the fire prevention point of view. A suitable spark control measures for this operation were required. We developed panels to minimize spark dispersion, shields to prevent the income of sparks to the pre-filter, and incombustible pre-filters. The equipment was tested and effectiveness was confirmed. This report provides the results of these tests.

Applicability of thermoelectric power generation system to Monju

Aizawa, Tatsuhiko*; Yamamoto, Shigeo*; Kim, S.*; Yang, J.*; Iwasako, Yasushi*; Toda, Shinichi; Kasagawa, Yusuke; Sakata, Hideaki; Oketani, Kazuhiro*

JNC TY4400 2003-003, 100 Pages, 2003/08

JNC-TY4400-2003-003.pdf:14.97MB

How to utilize the waste of heat is one of the most important issues for nuclear engineering. Its technological impact is significant in reduction of environmental burdens and minimization of CO2 emission through nuclear power generation with high efficiency. Research and development for thermoelectric power generation still weighs its importance on the search for high figure-of-merit materials; many engineering issues are still present to be solved toward promising solution to engineering issues are still present to be solved toward promising solution to engineering demand from market. Inthis study, new engineering ideas are proposed to make full use of heat waste via the prototype system for thermoelectric power generation. Sodium loop at the International Cooperation and Technology Development Center of Tsuruga Head Office in JNC was used as a heat source to demonstrate the effectiveness of the developed prototype system. The present research activities are categorized by the following elements.

Improvement of the MSG code for the MONJU Evaporators; Additional function of reverse flow calculation on water/steam model and animation for post processing

Toda, Shinichi; Yoshikawa, Shinji; Watanabe, Osamu*; Kishida, Masako*; Oketani, Kazuhiro*

JNC TN4400 2003-005, 106 Pages, 2003/05

JNC-TN4400-2003-005.pdf:3.82MB

The improved version of the MSG code(Multi-dimensional Thermal-hydroulic Analysis Code for Steam Generators) has been released. It has been carried out to improve based on the original version in order to calculate reverse flow on water/steam side, and to animate the post-processing data. To calculate reverse flow locally, modification to set pressure at each divided node point of water/steam region in the helical-coil heat tansfer tubes has been carried out. And the matrix solver has been also improved to treat a problem within practical calculation time against increasing the pressure points. In this case pressure and enthalpy have to be calculated simultaneously, however, it was found out that using the bloci-Jacobean method make a diagonal-dominant matrix, and solve the matriz efficiently with a relaxation method. As the result of calculations of a steady-state condition and a transient of SG blow down with manual tip operation, the improvement on calculation function of the MSG code was confirmed. And an animation function of temperature contour in the sodium shell side as a post procssing has been added. Since the animation is very effective to understand themal-hydraulic behavior on the sodium shell side of the SG, especially in case of transient condition, the analysis and evalution of the calculation results will be enabled to be more quickly and effectively.

Development of an fuel handling system for commercialized fast breeder reactor, 2; Conceptual design of in-vessel fuel handling system

Chikazawa, Yoshitaka; Konomura, Mamoru; Usui, Shinichi; Tozawa, Katsuhiro*; Hori, Toru*; Toda, Mikio*; Ikeda, Hirotsugu*

no journal, , 

no abstracts in English

Concept study on fuel handling system of commercialized sodium cooled reactor, 4; Study on spent fuel cleaning and water loading system

Tozawa, Katsuhiro*; Hori, Toru*; Toda, Mikio*; Chikazawa, Yoshitaka; Usui, Shinichi; Ikeda, Hirotsugu*

no journal, , 

no abstracts in English