Refine your search:     
Report No.
 - 
Search Results: Records 1-4 displayed on this page of 4
  • 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

Evaluation of tensile and creep properties on 9Cr-ODS steel claddings

Yano, Yasuhide; Hashidate, Ryuta; Tanno, Takashi; Imagawa, Yuya; Kato, Shoichi; Onizawa, Takashi; Ito, Chikara; Uwaba, Tomoyuki; Otsuka, Satoshi; Kaito, Takeji

JAEA-Data/Code 2021-015, 64 Pages, 2022/01

JAEA-Data-Code-2021-015.pdf:2.6MB

From a view point of practical application of fast breeder reactor cycles, which takes advantage of safety and economic efficiency and makes a contribution of volume reduction and mitigation of degree of harmfulness of high-level radioactive waste, it is necessary to develop fuel cladding materials for fast reactors (FRs) in order to achieve high-burnup. Oxide dispersion strengthened (ODS) steel have been studied for use as potential fuel cladding materials in FRs owing to their excellent resistance to swelling and their high-temperature strength in Japan Atomic Energy Agency. It is very important to establish the materials strength standard in order to apply ODS steels as a fuel cladding. Therefore, it is necessary to acquire the mechanical properties such as tensile, creep rupture strength tests and so on. In this study, tensile and creep rupture strengths of 9Cr-ODS steel claddings were evaluated using by acquired these data. Because of the phase transformation temperature of 9Cr-ODS steel, temperature range for the evaluation was divided into two ones at AC1 transformation temperature of 850$$^{circ}$$C.

Journal Articles

Failure time for Hastelloy XR under various loading at high temperatures

Kikuchi, Kenji; Kaji, Yoshiyuki;

Proc. of Int. Conf. on Materials and Mechanics'97 (ICM&M'97), p.607 - 612, 1997/00

no abstracts in English

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

4 (Records 1-4 displayed on this page)
  • 1