Investigation of the properties of high temperature resistance alloys used in the helium gas cooled high temperature reactor

Uwaba, Tomoyuki

JNC TN9420 2000-005, 28 Pages, 2000/03

JNC-TN9420-2000-005.pdf:0.94MB

In the first phase of the feasibility study, their basic objectives are presentating the feasible image and scenario of development of the FBR cycle system, which is composed of the fast reactor, spent fuel reprocessing and fuel manufacturing facility. In the development of the FBR system in this phase, various ideas of plants are to be studied, which include coolant types such as sodium, heavy metals, gases(CO, He), wator, and middle or small size of the reactor, and fuel types (MOX, metal and nitride). In this report, as a part of this study, materials used for the core of the helium gas cooled reactor and their integrity (corrosion, mechanical and irradiation property) under high temperature helium atmosphere were investigated from open literatures.

Effect of minor elements on corrosion behavior of Ni-Cr-W superalloys in HTGR helium

Tsuji, Hirokazu; ; Tsukada, Takashi; Nakajima, Hajime

JAERI-M 91-136, 42 Pages, 1991/09

JAERI-M-91-136.pdf:3.23MB

no abstracts in English

Corrosion behaviour of high temperature alloys in impure helium environments

Shindo, Masami; W.J.Quadakkers*; H.Schuster*

Journal of Nuclear Materials, 140, p.94 - 105, 1986/00

https://doi.org/10.1016/0022-3115(86)90237-0

no abstracts in English

Kinetics of Carbon Transfer Btween Uranium carbide fuel and stainless steel bonded with sodium

;

JAERI-M 4438, 14 Pages, 1971/05

JAERI-M-4438.pdf:0.42MB

no abstracts in English