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Kato, Shoichi; Sakurai, Tadashi*; Yoshida, Eiichi
JNC TN9400 2003-107, 127 Pages, 2004/02
JNC-TN9400-2003-107.pdf:29.28MB
An oxide dispersion strengthened(ODS) ferritic steel have excellent resistance to swelling and superior creep strength, they are expected to be used as a long-life cladding material in future advallced fast reactor. In this study, sodium environmental effect on the ODS steel developed by JNC were clarified through tensile test after sodium exposure for maximum 10,000hrs and creep-rupture test in sodium at elevated temperature. The exposure to sodium was conducted using a sodium test loop constituted by austenitic steels. For the conditions of sodium exposure test, the sodium temperatures were 923K and 973K, the oxygen concentration in sodium was below 2ppm and sodium flow rate on the surface of specimen was less than 1
10 sup-4 m/s. Further the specimen with the nickel diffused was prepared, which is simulate to nickel diffusing through sodium from the surface of structural stainless steels. The main results obtained were as follows;(1)The results showed excellent sodium-resistance up to a high temperature of about 973K in stagnant sodium conditions, and its considered that the effects of sodium environment on tensile properties were negligible. In case of stagnant sodium condition, creep-rupture strength in sodium was equal to the in argon gas, and no sodium environmental effect was observed. The same is true for the creep-rupture ductility. (2)The tensile properties of nickel diffused test specimens at high temperatures simulating microstructure change were equal to that of the thermal aging process specimens. These tensile tests suggest that sodium environmental effects can be ignored. However, the effect of nickel diffusion on creep strength are not clear at present and experimental investigation are being conducted. (3)The coefficient of nickel diffusion in the ODS steel can be estimated based on the results of nickel concentration measurement. This value is larger than that of the diffusion coefficient for typical alpha-Fe steel at temperature below 973
; Yoshida, Eiichi; Sakurai, Tadashi*; Yaguchi, Katsumi*
JNC TN9450 2003-001, 192 Pages, 2003/03
JNC-TN9450-2003-001.pdf:11.59MB
In order to evaluation of high temperature creep strength, creep tests under internal pressure on the fuel cladding tube for fast breeder reactor (FBR) has been preformed in New Technology Development Group. In this report, the result of the creep and creep-rupture properties on the advance austenitic stainless and high-Ni steels obtained up to this time was collected. Valuable test data totals 149 points including sodium environment test data. These data will be reflected in development and design for fuel cladding material. Contents of the data sheet are as follows ; (1)Material and number of data: 15Cr-20Ni steel (2 heats) 72 points, PNC1520 steel (1 heats) 6 points, 14Cr-25Ni steel (8 heats) 56 points, High-Ni steel (1 heat) 15 points (2)Test environment : In-air, In-argon gas and In-sodium (3)Test temperature : 600
C to 750C(873K to 1023K)
Yoshida, Eiichi; Sakurai, Tadashi*; Shibahara, Itaru
JNC TN9400 2003-050, 77 Pages, 2003/03
JNC-TN9400-2003-050.pdf:5.93MB
Sodium-bond double porous-plug is one of the candidates in development of the long-life life control rod for prototype reactor MONJU. Gas hold pressure and sodium penetration pressure of the porous-plug in liquid sodium are an important factor which determines the filling up of sodium into porous-plug and the gas plenum length in control rod pin. In this study, the fundamental characteristic of porous-plug was clarified by experiment in high temperature sodium. Moreover, the characteristic equation of design for a porous-plug was evaluated based on the obtained data.
; ; *; *; Yoshida, Eiichi;
PNC TN9450 92-004, 37 Pages, 1992/06
High Strength Ferritic/Martensitic Steel is one of the cardidate core materials for largescale FBR because of excellent resistance to swelling. This report are presented about the internal pressure creep of High Strength Ferritic/Martensitic Steel based on the R&D results obtained through the activities of material tests. Contents of the data sheet are as follows; (1) Material: High Strength Ferritic/Martensitic Steel Fuel cladding tube (
6.50.47.mm
) (2) Environment: In Air and In Sodium (3) Test temperature: 600 and 650C (4) Hoop stress: 9.48
32.43 kgf/㎜
(5) Number of data: 13 points