Refine your search:     
Report No.
 - 
Search Results: Records 1-7 displayed on this page of 7
  • 1

Presentation/Publication Type

Initialising ...

Refine

Journal/Book Title

Initialising ...

Meeting title

Initialising ...

First Author

Initialising ...

Keyword

Initialising ...

Language

Initialising ...

Publication Year

Initialising ...

Held year of conference

Initialising ...

Save select records

JAEA Reports

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 550$$^{circ}$$C 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 ...

JAEA Reports

The evaluation of material base standard of ODS ferritic stainless steel core component for fast breeder reactors

Mizuta, Shunji; ;

JNC TN9400 2000-048, 28 Pages, 2000/04

JNC-TN9400-2000-048.pdf:0.64MB

ODS (Oxide Dispersion Strengthened) ferritic-martainsitic steels are one of the most prospective cladding materials for advanced fast breeder reactors, since they are expected to have excellent swelling resistance and superior high temperature strength due to the finely distributed stable oxide particles(Y$$_{2}$$O$$_{3}$$). Properties and the tentative strength equations for ODS ferritic-martainsitic were proposed on the basis of the latest data to apply to the feasibility study of the sodium coolant MOX fuel plant. The items of equations are follows. (1)creep rupture strength (2)correction factor of creep rupture strength (in Na and in reactor) (3)outer surface eorrosion (Na) (4)inner surface corrosion (in MOX fuel pin) (5)thermal conductivity

JAEA Reports

Microstructural assessment of damaged materials in FBR assessment of creep damage in weldment

Momma, Yoshio*; *; ; ; ; Aoto, Kazumi

JNC TN9400 2000-044, 22 Pages, 2000/03

JNC-TN9400-2000-044.pdf:1.37MB

ln the past the microstructural observation was mostly applied to understand the materials behavior qualitatively in R&D of the new materials and the life prediction for the fast breeder reactor components. However, the correlation between the changes in properties and microstrutures must be clarified to ensure the structural integrity. Particularly we are interested in the method to correlate the long-term properties and microstructural changes at high temperatures. The current research is to quantify the changes in microstructure of the weld metal for the welded structure of the reactor vessel. ln this research we have conducted creep testing of the weld metals at 823 and 873K up to 37,000h. Two types of the weld metals (16Cr-8Ni-2Mo and 18Cr-12Ni-Mo) were subjected to the creep testing. Based on the areas of the precipitates, the microstructural characterization with time and creep damage was attempted. The creep strength of the 16Cr-8Ni-2Mo weld metal is lower than that of the 18Cr-12Ni-Mo one at higher stresses, shorter times. But there is a trend toward to become similar strength with lower stresses and increasing times. The creep-rupture ductility of the 16Cr-8Ni-2Mo weld metal is superior to that of the 18Cr-12Ni-Mo one. The creep-rupture takes place at the interface of the sigma ($$sigma$$) phases precipitated in the delta ($$delta$$) ferrites at 823K lower stresses and 873K. The amount of precipitates in the 16Cr-8Ni-2Mo weld metal is smaller than that in the 18Cr-12Ni-Mo one at each temperature and stress. Also it is apparent that the amount of the precipitates is primarily responsible to the decomposition of the $$delta$$ phase, because the amount of the residual $$delta$$ ferrites measured by the Magne-Gauge reduces with times. Using the Larson-Miller parameter it was possible to correlate the amount of the precipitates linearly with the LMP values.

JAEA Reports

Fatigue properties of Mod.9Cr-1Mo steel; Result of low-cycle fatigue test in air

Furukawa, Tomohiro; ; Yoshida, Hidekazu;

PNC TN9410 93-042, 56 Pages, 1993/02

PNC-TN9410-93-042.pdf:3.36MB

Mod.9Cr-1Mo steel is a candidate material of once-through type steam generators for the Fast Breeder Reactors, and it is required to clarify low-cycle fatigue properties in air at high temperature on this material for structural design. So the tests were carried out for three heats (12mmt plate, 25mmt plate and 250mmt forged) on conditions that temperature is 450$$sim$$650$$^{circ}$$C and strain range is 0.4$$sim$$1.2%. Results obtained are su㎜araized as follows. (1)For cyclic stress-strain behavior of Mod.9Cr-1Mo steel cyclic hardening was. observed in the early stage, and after that changed to softening to failure. The behavior was similar to normalized and tempered 2.25Cr-1Mo steel. (2)Low-cycle fatigue strength of Mod.9Cr-1Mo steel in air was remarkably higher than that of 2.25Cr-1Mo steel, and almost same as much as that of SUS304 steel. Moreover, fatigue life of Mod.9Cr-1Mo steel was longer than that of 9Cr-2Mo or Low C-9Cr-1Mo-Nb-V steel under low strain conditions. (3)In the case of Mod.9Cr-1Mo forged steel, the influence of the sampling position and direction of specimens was not effective. These results were reflected to prepare of tentative material strength standard in 1992.

JAEA Reports

Materials properties data sheet (No.Q 01); Internal pressure creep properties data on high strength ferritic/martensitic steel in air and in sodim

; ; *; *; Yoshida, Eiichi;

PNC TN9450 92-004, 37 Pages, 1992/06

PNC-TN9450-92-004.pdf:0.78MB

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 ($$phi$$6.5$$times$$0.47.mm$$^{t}$$) (2) Environment: In Air and In Sodium (3) Test temperature: 600 and 650$$^{circ}$$C (4) Hoop stress: 9.48$$sim$$32.43 kgf/㎜$$^{2}$$ (5) Number of data: 13 points

Journal Articles

Neutron irradiation effects on fusion reactor materials

Shiraishi, K.

Oyo Butsuri, 55(3), p.202 - 209, 1986/00

no abstracts in English

Oral presentation

Material properties of weld joints of reduced activation ferritic/martensitic steel, F82H

Hirose, Takanori; Sakasegawa, Hideo; Nakajima, Motoki; Tanigawa, Hiroyasu

no journal, , 

Weld joints of a reduced activation ferritic/martensitic steel, F82H were prepared using Tungsten-Inert-Gas (TIG) and Electron Beam (EB) welding. Physical properties and mechanical properties of these weld joints were investigated in this work. Moreover, effects of Post Weld Heat Treatment (PWHT) was also investigated. After PWHT at 720 $$^{circ}$$C, most of physical properties of weld metal were very similar to those of F82H base metal. Coefficient of thermal expansion and thermal diffusivity of weld metal demonstrated 10% of degradation compared to the base metal. Although weld metal and heat affected zone heated above transformation temperature demonstrated hardening and embrittlement, PWHT above 750 $$^{circ}$$C successfully moderated the hardening without softening in the base metal.

7 (Records 1-7 displayed on this page)
  • 1