Research on development of high-purity iron-based alloys; Manufacture, analysis of small amount of element and property tests

; *; ; ; Aoto, Kazumi;

JNC TN9400 2000-059, 43 Pages, 2000/05

JNC-TN9400-2000-059.pdf:2.08MB

The purpose of this study is to understand the material properties of manufacturable high-purity iron and high-purity iron-based alloy in present technology and to get an applicable prospect for the structural and functional material of the frontier fast reactor. Then the about 10kg high-purity iron and iron-based alloy were melted using a cold-crucible induction melting furnace under the ultra-high vacuum. Subsequent to that, the compatibility between the melted material and the high-temperature sodium environment which is a special feature of the fast reactor and tensile property at room and elevated temperatures were investigated using the melted materials. Also, the creep test using the high-purity 50%Cr-Fe alloy at 550C in air in order to understand the high temperature creep property. ln addition, the material properties such as thermal expansion coefficient, specific heat and electrical resistance were measured and to evaluate the outlook for the structural material for the fast reactor. The following results were obtained based on the property test and evaluation. (1)lt was possible to melt the about 10kg high-purity ingot and high-purity 50%Cr-Fe alloy ingot using a cold-crucible induction melting furnace under the ultra-high vacuum. (2)The tensile tests of the high-purity 50%Cr-Fe alloy were performed at room and elevated temperatures in order to understand the deformation behavior. From the experimental results, it was clear that the high-purity 50%Cr-Fe alloy possesses high strength and good ductility at elevated temperatures. (3)The physical properties (the thermal expansion coefficient and specific heat etc.) were measured using the high-purity 50%Cr-Fe alloy. lt was clear that the thermal expansion coefficient of high-purity 50%Cr-Fe alloy was smaller than that of SUS304. (4)From the corrosion test in liquid sodium, the ordinary-purity iron showed the weight loss after corrosion test. However the high-purity iron showed ...

Irradiation damage in nuclear graphite and carbon material; Changes in dimension and physical properties caused by neutron irradiation and heat treatment

Matsuo, Hideto

Tanso, 0(150), p.290 - 302, 1991/00

https://doi.org/10.7209/tanso.1991.290

no abstracts in English

Irradiation-induced property changes of thermally oxidized nuclear graphites

; ;

Journal of Nuclear Materials, 152, p.283 - 288, 1988/00

https://doi.org/10.1016/0022-3115(88)90338-8

no abstracts in English

Effect of oxidation on physical properties of nuclear grade graphites

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Journal of Nuclear Materials, 136, p.229 - 237, 1985/00

https://doi.org/10.1016/0022-3115(85)90010-8

no abstracts in English

Effect of heat treatment on physical properties of carbon material for use as thermal barrier in the VHTR(very high temperature gas-cooled reactor)

;

High Temperatures-High Pressures, 16, p.695 - 705, 1984/00

no abstracts in English

Dimensional change of carbon material under compressive stress at high temperatures

; ;

High Temperatures-High Pressures, 15, p.707 - 714, 1983/00

no abstracts in English

Studies on the Core-Support Carbon Material for use in VHTR,1; The Change of Thermal Conductivity and Electrical Resistivity due to Heat Treatment

; ; ; ; *

JAERI-M 8551, 15 Pages, 1979/11

JAERI-M-8551.pdf:0.69MB

no abstracts in English