Results 61 to 70 of about 209 (131)

Efficiency of thermal outgassing for tritium retention measurement and removal in ITER

Nuclear Materials and Energy, 2017
As a licensed nuclear facility, ITER must limit the in-vessel tritium (T) retention to reduce the risks of potential release during accidents, the inventory limit being set at 1kg.
G. De Temmerman, M.J. Baldwin, D. Anthoine, K. Heinola, A. Jan, I. Jepu, J. Likonen, C.P. Lungu, C. Porosnicu, R.A. Pitts   +9 more
doaj   +1 more source

HICU PIE results of neutron-irradiated lithium metatitanate pebbles

Nuclear Materials and Energy
Lithium metatitanate (Li2TiO3) pebbles were irradiated with neutrons within the HICU (High neutron fluence Irradiation of pebble staCks for fUsion) experiment to investigate their material properties and tritium release behaviour in a post-irradiation ...
Julia Leys, Rolf Rolli, Hans-Christian Schneider, Regina Knitter   +3 more
doaj   +1 more source

Study on the radiological effect of the tritium gas released from fussion reactor

He jishu
BackgroundThe amount of gaseous tritium stored and released in fusion reactor is higher than that in current fission reactors, so that tritium is an important source of potential radioactivity in fusion reactor.PurposeThis study aims to investigate the ...
ZUO Qingning, HUANG Jingyun, ZHANG Junnan, WANG Xiaoliang, BAI Xiaoping, WEI Qiming   +5 more
doaj   +1 more source

Estimation and Mode Selection of Deuterium Flux Supply into Ampoule Device Through Diffusion Filter in Experiments with Pb15.7Li Eutectic at the IVG1.M Reactor

Eurasian Chemico-Technological Journal, 2019
One of the most promising materials to produce tritium in fuel cycle of fusion facilities is the lead-lithium eutectic Pb15.7Li. Tritium will be generated in nuclear reactions in a lithium-containing material under the influence of neutron irradiation ...
Ye. Tulubayev, Yu. Ponkratov, M. Skakov, Yu. Gordienko, Zh. Zaurbekova   +4 more
doaj   +1 more source

Research on the optimization method of tritium release efficiency in a water cooled blanket for CFETR

AIP Advances
The Chinese Fusion Engineering Test Reactor (CFETR) is a tokamak device located between ITER and DEMO, with the primary goal of generating useable fusion energy through D–T reactions.
Jie Li, Xianbing Xiang, Xiaoyi Zeng, Haiyan Yang, Jie Zhang   +4 more
doaj   +1 more source

Determination of tritium inventory in carbon divertor tiles used in deuterium plasma experiment by induction heating method

Nuclear Materials and Energy
The tritium inventory of the plasma-facing materials in a Large Helical Device (LHD) was analyzed using a thermal desorption system. In this study, we developed an induction heating system for the thermal desorption of tritium from carbon divertor tiles,
Masahiro Tanaka, Hiromi Kato, Naoyuki Suzuki, Hiroki Chimura, Hiroaki Yonezu, Suguru Masuzaki   +5 more
doaj   +1 more source

Tritium Release from Improved Ceramic Tritium Breeder with Catalytic Function [PDF]

Journal of Nuclear Science and Technology, 1999
Kenzo MUNAKATA, Atsushi BABA, Takahiro KAWAGOE, Toshiharu TAKEISHI, Yoshihiro YOKOYAMA, Masabumi NISHIKAWA, Ralf Dieter PENZHORN, Hirotake MORIYAMA, Keizo KAWAMOTO, Kenji OKUNO   +9 more
openaire   +1 more source

TGA study of high-temperature corrosion behavior of neutron-irradiated Be

Nuclear Materials and Energy
This paper investigates the high-temperature corrosion of neutron-irradiated titanium beryllide B e 12 T i in a vapor-argon environment, emphasizing the kinetics of mass loss and the forms of released tritium.
Asset Shaimerdenov, Saulet Askerbekov, Zhanar Bugybay, Assyl Akhanov, Magzhan Aitkulov, Yevgen Chikhray, Timur Kulsartov, Inesh Kenzhina, Zhanna Zaurbekova, Manarbek Kylyshkanov   +9 more
doaj   +1 more source

Development and validation of a program for assessing the consequences of radioactivity releases from fusion reactor accidents

Fushe yanjiu yu fushe gongyi xuebao
The deuterium-tritium fusion reaction is the fastest commercially achievable artificially controlled fusion reaction. However, tritium, as a fuel and neutron radiation-activated material, poses radioactive safety challenges.
CUI Weijie, ZHANG Jinlong, LI Zaixin, CAO Bo   +3 more
doaj   +1 more source

MATHEMATICAL MODELLING OF PROCESSES OF BURNING OUT, GENERATION AND RELEASE TRITIUM IN CONDITIONS REACTOR IRRADIATION

Вестник. Серия физическая, 2008
Goal of this work is mathematical modelling of processes of burning out, generation and release tritium from the irradiated lithium ceramics samples. is shown, that metatitanate lithium are most perspective a material for their application in zones of ...
I. Beckman, I. Tazhibayeva, A. Kuykabaeva, I. Buntseva   +3 more
doaj