Employing of ZrCo as a fuel source in a discharge-type fusion neutron source operated in self-sufficient mode

被引：13
作者：
Kenjo, Shunsuke [1 ,3 ]
Ogino, Yasuyuki [1 ]
Mukai, Keisuke [2 ]
Bakr, Mahmoud [2 ,4 ,5 ]
Yagi, Juro [2 ]
Konishi, Satoshi [2 ]
机构：
[1] Kyoto Univ, Grad Sch Energy Sci, Uji, Kyoto 6110011, Japan
[2] Kyoto Univ, Inst Adv Energy, Uji, Kyoto 6110011, Japan
[3] Natl Inst Quantum & Radiol Sci & Technol, Aomori, Japan
[4] Assiut Univ, Fac Sci, Phys Dept, Assiut 71516, Egypt
[5] Galala Univ, Fac Sci, Alsokhna 43511, Egypt
来源：
INTERNATIONAL JOURNAL OF HYDROGEN ENERGY | 2022年 / 47卷 / 05期
基金：
日本学术振兴会;
关键词：
Intermetallic compound; Hydrogen storage; Hydrogen isotope effect; Nuclear fusion; Neutron source; STORAGE PROPERTIES; DISPROPORTIONATION BEHAVIOR; THERMAL-STABILITY; TRITIUM STORAGE; HYDROGEN; NI; RECOVERY; SURFACE; SYSTEM; DEVICE;
D O I：
10.1016/j.ijhydene.2021.10.250
中图分类号：
O64 [物理化学（理论化学）、化学物理学];
学科分类号：
070304 ; 081704 ;
摘要：
A discharge-type fusion neutron source generates neutrons by fusion reactions of hydrogen isotope atoms. In order to operate the fusion device based on the deuterium -tritium (D-T) fusion reaction, the tritium inventory is required to be decreased. In the present work, a self-sufficient system was installed into the fusion device for reducing the amount of hydrogen isotope fuel gas. The fuel gas was supplied and recovered with an intermetallic compound ZrCo in a sealed chamber in this system. A deuterium-deuterium operation was maintained for more than 60 min with stable discharge voltages, and the temperature of the ZrCo bed was changed to improve the neutron production rate. Factors that influenced the pressure inside the chamber were determined and optimized. Gas analysis using a quadrupole mass spectrometer indicates a dilution of the deuterium fuel was caused by hydrogen isotope exchange between the supplied deuterium gas and the absorbed protium on the chamber and electrodes surface. This system's hydrogen isotope control method and the amount of fuel were proposed for a D-T operation. (c) 2021 Hydrogen Energy Publications LLC. Published by Elsevier Ltd. All rights reserved.
引用
收藏
页码：3054 / 3062
页数：9
相关论文
共 42 条
[1]   Characterization of an ultra-compact neutron source based on an IEC fusion device and its prospective applications in radiography [J].
Bakr, Mahmoud ;
Mukai, Keisuke ;
Masuda, Kai ;
Yagi, Juro ;
Konishi, Satoshi .
FUSION ENGINEERING AND DESIGN, 2021, 167
[2]   Evaluation of 3D printed buckyball-shaped cathodes of titanium and stainless-steel for IEC fusion system [J].
Bakr, Mahmoud ;
Wulfkuehler, Jan-Philipp ;
Mukai, Keisuke ;
Masuda, Kai ;
Tajmar, Martin ;
Konishi, Satoshi .
PHYSICS OF PLASMAS, 2021, 28 (01)
[3]   Improvement of the Neutron Production Rate of IEC Fusion Device by the Fusion Reaction on the Inner Surface of the IEC Chamber [J].
Bakr, Mahmoud ;
Masuda, Kai ;
Yoshida, Masaya .
FUSION SCIENCE AND TECHNOLOGY, 2019, 75 (06) :479-486
[4]   On the thermal stability of the zirconium/cobalt-hydrogen system [J].
Bekris, N ;
Besserer, U ;
Sirch, M ;
Penzhorn, RD .
FUSION ENGINEERING AND DESIGN, 2000, 49-50 :781-789
[5]   SURFACE ANALYTICAL CHARACTERIZATION OF THE HYDROGEN GETTER MATERIAL ZRCO [J].
BREDENDIEKKAMPER, S ;
KLEWENEBENIUS, H ;
PFENNIG, G ;
BRUNS, M ;
DEVILLERS, M ;
ACHE, HJ .
FRESENIUS ZEITSCHRIFT FUR ANALYTISCHE CHEMIE, 1989, 335 (07) :669-674
[6]   Hydriding and dehydriding characteristics of small-scale DU and ZrCo beds [J].
Chung, Dongyou ;
Lee, Jungmin ;
Koo, Daeseo ;
Chung, Hongsuk ;
Kim, Ki Hwan ;
Kang, Hyun-Goo ;
Chang, Min Ho ;
Camp, Patrick ;
Jung, Ki Jung ;
Cho, Seungyon ;
Yun, Sei-Hun ;
Kim, Chang Shuk ;
Yoshida, Hiroshi ;
Paek, Seungwoo ;
Lee, Hansoo .
FUSION ENGINEERING AND DESIGN, 2013, 88 (9-10) :2276-2279
[7]   CHARACTERIZATION OF THE ZRCO-HYDROGEN SYSTEM IN VIEW OF ITS USE FOR TRITIUM STORAGE [J].
DEVILLERS, M ;
SIRCH, M ;
BREDENDIEKKAMPER, S ;
PENZHORN, RD .
CHEMISTRY OF MATERIALS, 1990, 2 (03) :255-262
[8]   Energy distributions and radiation emissions in an inertial electrostatic confinement (IEC) device under low and moderate magnetic fields [J].
Dursun, Bekir ;
Kurt, Erol ;
Kurt, Hilal .
INTERNATIONAL JOURNAL OF HYDROGEN ENERGY, 2017, 42 (28) :17874-17885
[9]   Required, achievable and target TBR for the European DEMO [J].
Fischer, U. ;
Boccaccini, L., V ;
Cismondi, F. ;
Coleman, M. ;
Day, C. ;
Hoerstensmeyer, Y. ;
Moro, F. ;
Pereslavtsev, P. .
FUSION ENGINEERING AND DESIGN, 2020, 155
[10]   SURFACE ANALYTICAL INVESTIGATION OF THE TRITIUM GETTER ZRCO AFTER EXPOSURE TO VARIOUS GASES [J].
GLASBRENNER, H ;
KLEWENEBENIUS, H ;
BRUNS, M ;
PFENNIG, G ;
PENZHORN, RD ;
ACHE, HJ .
MIKROCHIMICA ACTA, 1992, 107 (3-6) :207-217
12345