Abstract
International Thermonuclear Experimental Reactor (ITER) project plans to utilize beryllium as a plasma facing material, because of its prominent advantages such as low Z, substantial oxygen gettering effect and low tritium trapping in the process of redeposition. Beryllium would also be essential as the neutron multiplier to achieve tritium breeding ratio higher than unity of solid breeder blanket. High temperature chemical compatibility of beryllium with various gases, metals and ceramics is the major concerns in the design of first wall, divertor and blanket as well as safety analysis in case of accidents such as LOCA (loss-of-coolant accident) and LOVA. The present paper reviews the following subjects from viewpoint of thermodynamic database and chemical engineering of beryllium; (i) High temperature compatibility with gases (ii) High temperature compatibility with metals (iii) High temperature compatibility with oxide ceramics (iv) High temperature compatibility with lithium ceramics (v) Multi-component phase diagrams of beryllium-lithium ceramic systems. (author).
Yoshida, Hiroshi;
[1]
Okamoto, Makoto;
Odawara, Osamu;
Terai, Takayuki
- Japan Atomic Energy Research Inst., Naka, Ibaraki (Japan). Naka Fusion Research Establishment
Citation Formats
Yoshida, Hiroshi, Okamoto, Makoto, Odawara, Osamu, and Terai, Takayuki.
High temperature chemical compatibility of beryllium for fusion reactor material.
Japan: N. p.,
1993.
Web.
Yoshida, Hiroshi, Okamoto, Makoto, Odawara, Osamu, & Terai, Takayuki.
High temperature chemical compatibility of beryllium for fusion reactor material.
Japan.
Yoshida, Hiroshi, Okamoto, Makoto, Odawara, Osamu, and Terai, Takayuki.
1993.
"High temperature chemical compatibility of beryllium for fusion reactor material."
Japan.
@misc{etde_10150787,
title = {High temperature chemical compatibility of beryllium for fusion reactor material}
author = {Yoshida, Hiroshi, Okamoto, Makoto, Odawara, Osamu, and Terai, Takayuki}
abstractNote = {International Thermonuclear Experimental Reactor (ITER) project plans to utilize beryllium as a plasma facing material, because of its prominent advantages such as low Z, substantial oxygen gettering effect and low tritium trapping in the process of redeposition. Beryllium would also be essential as the neutron multiplier to achieve tritium breeding ratio higher than unity of solid breeder blanket. High temperature chemical compatibility of beryllium with various gases, metals and ceramics is the major concerns in the design of first wall, divertor and blanket as well as safety analysis in case of accidents such as LOCA (loss-of-coolant accident) and LOVA. The present paper reviews the following subjects from viewpoint of thermodynamic database and chemical engineering of beryllium; (i) High temperature compatibility with gases (ii) High temperature compatibility with metals (iii) High temperature compatibility with oxide ceramics (iv) High temperature compatibility with lithium ceramics (v) Multi-component phase diagrams of beryllium-lithium ceramic systems. (author).}
place = {Japan}
year = {1993}
month = {Feb}
}
title = {High temperature chemical compatibility of beryllium for fusion reactor material}
author = {Yoshida, Hiroshi, Okamoto, Makoto, Odawara, Osamu, and Terai, Takayuki}
abstractNote = {International Thermonuclear Experimental Reactor (ITER) project plans to utilize beryllium as a plasma facing material, because of its prominent advantages such as low Z, substantial oxygen gettering effect and low tritium trapping in the process of redeposition. Beryllium would also be essential as the neutron multiplier to achieve tritium breeding ratio higher than unity of solid breeder blanket. High temperature chemical compatibility of beryllium with various gases, metals and ceramics is the major concerns in the design of first wall, divertor and blanket as well as safety analysis in case of accidents such as LOCA (loss-of-coolant accident) and LOVA. The present paper reviews the following subjects from viewpoint of thermodynamic database and chemical engineering of beryllium; (i) High temperature compatibility with gases (ii) High temperature compatibility with metals (iii) High temperature compatibility with oxide ceramics (iv) High temperature compatibility with lithium ceramics (v) Multi-component phase diagrams of beryllium-lithium ceramic systems. (author).}
place = {Japan}
year = {1993}
month = {Feb}
}