Heavy-ion-induced bystander killing of human lung cancer cells; Role of gap junctional intercellular communication

Harada, Kosaku*; Nonaka, Tetsuo*; Hamada, Nobuyuki*; Sakurai, Hideyuki*; Hasegawa, Masatoshi*; Funayama, Tomoo; Kakizaki, Takehiko*; Kobayashi, Yasuhiko; Nakano, Takashi*

Cancer Science, 100(4), p.684 - 688, 2009/04

https://doi.org/10.1111/j.1349-7006.2009.01093.x

Remote handling design for moderator-reflector maintenance in JSNS

Teshigawara, Makoto; Aizawa, Hideyuki; Harada, Masahide; Kinoshita, Hidetaka; Meigo, Shinichiro; Maekawa, Fujio; Kaminaga, Masanori; Kato, Takashi; Ikeda, Yujiro

JAERI-Tech 2005-029, 24 Pages, 2005/05

JAERI-Tech-2005-029.pdf:3.38MB

This report introduces the present design status of remote-handling devices for activated and used components such as moderator and reflector in a spallation neutron source of the Material and Life Science Facility (MLF) at J-PARC. The design concept and maintenance scenario are also mentioned. A key maintenance scenario adopts that the used components should be taken out from the MLF to the other storage facility after the volume reduction of them. Almost full remote handling is available to the maintenance work except for the connection/disconnection pipes of the cooling water. Total six remote handling devices are used for moderator-reflector maintenance. They are also available to the proton beam window and muon target maintenance. Maintenance scenario is separated into two works. One is to replace used components to new ones during beam-stop and the other is dispose used components during beam operation. Required period of replacement work is estimated to be 15 days, on the other hand, the disposal work is 26 days after dry up work (30 days), respectively.

None

Wada, Yukio; Funasaka, Hideyuki; Myochin, Munetaka; Yamamoto, Kazunori; Harada, Hideo; ;

PNC TN8100 96-005, 16 Pages, 1996/01

PNC-TN8100-96-005.pdf:1.6MB

no abstracts in English

Analysis of bystander effect using high-LET heavy-ion microbeam

Harada, Kosaku*; Nonaka, Tetsuo*; Hamada, Nobuyuki*; Funayama, Tomoo; Sakurai, Hideyuki*; Wada, Seiichi*; Sakashita, Tetsuya; Hasegawa, Masatoshi*; Kobayashi, Yasuhiko; Nakano, Takashi*

no journal, , 

no abstracts in English

Experiments on microbes in TANPOPO mission on the International Space Station

Yokobori, Shinichi*; Kawaguchi, Yuko*; Harada, Miyu*; Murano, Yuka*; Tomita, Kaori*; Hayashi, Nobuhiro*; Tabata, Makoto*; Kawai, Hideyuki*; Okudaira, Kyoko*; Imai, Eiichi*; et al.

no journal, , 

no abstracts in English

Design evaluation of monitoring small specimens attached on the spallation target vessel for integrity examination plan and cutting device technical evaluation for volume reduction of high radiated materials

Nemoto, Hideyuki; Wakai, Eiichi; Kinoshita, Hidetaka; Masuda, Shiho; Harada, Masahide; Takada, Hiroshi; Ishikawa, Koji*; Imanari, Kei*; Ito, Takeshi*

no journal, , 

no abstracts in English

Development of experiment system for tritium release behavior from mercury spallation neutron target at J-PARC

Masuda, Shiho; Kai, Tetsuya; Harada, Masahide; Kinoshita, Hidetaka; Wakai, Eiichi; Nemoto, Hideyuki; Ikeda, Yujiro; Haga, Katsuhiro

no journal, , 

In the Materials and Life science experimental Facility at J-PARC, pulsed neutrons are provided by a mercury target via spallation reactions. During the target vessel replacement, gaseous spallation products are released from the mercury circulation system to outside. The release of radioactive gases needs to be reduced to a negligibly small level by a purging process in advance of replacement. The radioactivity of noble gases decreased by the purging process while that of tritium was almost unchanged. It is considered that most of tritium produced in mercury is accumulated in the vessel made of stainless-steel and is gradually desorbed during the purging and the vessel replacement. However, there have been no effective data associated with tritium behavior in an environment of mercury spallation target. Then, authors decided to develop an experimental system to understand these phenomena quantitatively and to discuss procedures to minimize tritium release during the vessel replacement. As a first step, we start experiments using deuterium before using tritium. Accumulation and release behaviors of deuterium to stainless-steel are examined under vacuum, controlled humidity and mercury coexistence conditions. Results are expected to be used to establish safer the target vessel replacement.