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JAEA Reports

Self-welding behavior of various materials in a sodium environment (IV) Development of self-welding equipment and its preliminary test

Mizobuchi, Shotaro*; Kano, Shigeki; Nakayama, Koichi; Namekawa, Masaru; Owada, Tetsuro*; Atsumo, Hideo

PNC TN941 75-13, 103 Pages, 1974/12

PNC-TN941-75-13.pdf:6.23MB

We developed and installed the self-welding equipment (SW-2) in self-welding Wearing Test Loop at the end of March, 1974, while had installed the wearing equipment at the end of March, 1972 and have continued to test in sodium and argon since then. SW-2 has the functions to simulate to the sliding and contact modes of LMFBR's components closelier than conventional equipments in foreign countries. The characteristics of SW-2 are as follow: (1)To be able to compress and self-weld materials in high temperature sodium and then to estimated self-weldability with the results of in-sodium tensile or in-sodium torsion tests of self-welded materials. (2)All of torsional, tensile and compressive loads can be gained by oil pressure units, and then the operation and structure of equipment became simple. (3)To be easily able to test in other environments (ex. in inert gas) by rolling the equipment of 180 degrees. (4)To be able to test under the normal load from less than 100kg to 4,000kg. Also, we conducted a part of the function test in high temperature argon and ascertained the performance of equipment to be satisfactory.

JAEA Reports

Self-welding behavior of various materials in a sodium environment (II); Weldability of hard alloy and carbide

Mizobuchi, Shotaro*; Kano, Shigeki; Namekawa, Masaru; Owada, Tetsuro*; Atsumo, Hideo

PNC TN941 74-18, 41 Pages, 1974/03

PNC-TN941-74-18.pdf:3.06MB

In this Experiment, We conducted Self-Welding Test about the Refractory Metal such as Tungsten, Molybdenum and Hard Metal (ex. Chrome-Carbide, Stellite No.6), Nickel, Niehrome. The Following Results were obtained. (1)Chrome-Carbide (coated with Detonation Gun) was effective as an Anti-Welding Material, but the Carbide with the content of Tungsten showed a strong Tendency to Self-Welding. (2)Tungsten and Molybdenum (coated with Wire Explosion Gun) were effective as Anti-Welding Materials. (3)Stellite No.6 combinated with Austenitic Stainless Steel (SUS316) showed a Tendency to Self-Welding. (4)Nickel and Nichrome were completely Self-Welded by the Formation of Diffusion Zone.

JAEA Reports

Wear tests of materials for FBR in sodium environment(II); Friction and wear of hard metals and carbides

Kano, Shigeki; *; Namekawa, Masaru; Owada, Tetsuro*; Atsumo, Hideo

PNC TN941 74-12, 57 Pages, 1974/03

PNC-TN941-74-12.pdf:1.68MB

In views of the limitation of use and the durability, it is necessary to use friction and wear resistant materials for sliding components of sodium cooled reactor. Therefore, it is required that we obtain friction and wear data about these materials in high temperature sodium. We tested about various combinations of Stellite No.6, Colmonoy No.6, Metco 16C, Deloro Stellite SF-60M, SUS304, LC-1C, LW-1N-40 and LW-5. The tests yielded the following results: (1)A certain material combination was different in behavior between friction and wear. (2)The combination of Derolo Stellite SF-60M vs. Colmonoy No.6 showed the lowest kinetic friction coefficient and specific wear rate of all combinations tested. (3)The combination of LC-1C vs. LC-1C showed the lowest static friction coefficient of all combinations tested. (4)The combination of LW-1N-40 vs. LW-1N-40 was unstable in behavior. (5)SUS 304 had the strongest self-weldability of all materials tested. (6)LW-5 was buckled during the test.

JAEA Reports

Self-Weding behavior of various materials in a sodium environment; Self-welding of SUS316 and hard chrome plating

*; Kano, Shigeki; Namekawa, Masaru; Owada, Tetsuro*; Atsumo, Hideo

PNC TN941 73-32, 38 Pages, 1973/08

PNC-TN941-73-32.pdf:6.98MB

Self-Welding occurs at the contact surface point of two materials in high-temperature sodium. In this experiment We conducted as to self-welding tendencies of the candidate materials for the fuel-assembly pad in high temperature Sodium. The results obtained are as follows: (1)Austenitic stainless steel (SUS316) showed a marked tendency to self-weld at 600$$^{circ}$$C, and some different material couples with SUS420 and Cr$$_{3}$$C$$_{2}$$ (coated with plasma-spray) were self-welded by the formation of diffusion layer. (2)Hard chrome plating material couples with austenitic stainless steel showed tendency to self-welding, but the same material couples showed little welding. (3)Numerous crackings were showed on surface layer of the hard chrome plating after sodium immersion test. (4)Molybdinum and Hard alloy materials showed no-self welding.

JAEA Reports

Corrosion behavior of the cladding tube (AISI Type-316SS) for FBR in high temperature sodium; Experimental studies on the oxygen concentration dependence of the corrosion in sodium

*; Kano, Shigeki; Owada, Tetsuro*; Atsumo, Hideo

PNC TN941 73-24, 64 Pages, 1973/07

PNC-TN941-73-24.pdf:4.71MB

Some experiments in order to investigate the oxygen concentration dependence of the corrosion in sodium were carried out on the domestic cladding tube (nominal dimension of 6.3 mm outside diameter at 0.35 mm wall thickness) of Type-316 stainless steel. The daughter loops, M-2 and M-11, were used for mass-transfer test of the tube specimen, in which the test condition was individually selected on the oxygen concentration; the cold trap temperature was controlled to keep its concentration at 200$$^{circ}$$C in M-2 and 150$$^{circ}$$C in M-11. Mass-transfer test was made up to about 2000 hours in flowing sodium and the maximum temperature of test sections was held at 650$$^{circ}$$C. After exposure in sodium, the following analyses were made on the specimens: weighing, surface roughness, SEM, X ray, X ray microscan, mechanical properties and others. The results obtained after exposure at 650$$^{circ}$$C are summarlized as follows: (1)General corrosion rate of the cladding tube speoimen is remarkably dependent on the oxygen concentration. It shows distinguished increase as the cold-trap temperature increases. (2)The leaching layer of iron was observed, in which alloying elements were depleted in nickel and chromium. Elemental leaching and depletion in the surface layer was mainly observed inwards along the grain boundary in the neighbour of the surface exposed in sodium. Thickness of the leaching layer was about 30 $$mu$$m. (3)At the surface layer of the specimens exposed in sodium, the presence of ferrite was confirmed by X ray, and the surface roughness of the specimens after exposure in the higher oxygen concentration increased to about 1.8 times as large as those before exposure.

JAEA Reports

Wear tests of materials for FBR in sodium environment(I); Wear of hard metals

Kano, Shigeki; Mizobuchi, Shotaro*; Namekawa, Masaru; *; Atsumo, Hideo; Owada, Tetsuro*

PNC TN941 73-17, 99 Pages, 1973/06

PNC-TN941-73-17.pdf:3.57MB

In views of the limitation of use and the durability, it is necessary to use wear resistant materials for sliding components of sodium cooled reactors. Therefore, it is required that we obtain wear data about these materials in high temperature sodium. We conducted wear tests about various pairs of hard metals (stellite No.1, stellite No.6, colmonoy No.5 and colmonoy No.6). The tests yielded the following results: (1)The specific wear rate was less and the friction coefficient was lower and more stable in the test about a pair of hard metals (Colmonoy No.5 & No.6) than about both pairs of SUS304 coupled with stellite No.1 and Colmonoy No.6. (2)The friction coefficient was lower in the test about the pair of SUS304 coupled with stellite No.1 than coupled with colmonoy No.6. (3)The friction-affected Layer was found on the sliding surface. (4)The appearance of the sliding surface was considerably different between in sodium and in argon.

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