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 850C.

Dataset of the relationship between unconfined compressive strength and tensile strength of rock mass

Sugita, Yutaka; Yui, Mikazu

JNC TN8450 2001-007, 16 Pages, 2002/02

JNC-TN8450-2001-007.pdf:0.78MB

This report summary the dataset of the relationship between unconfined compressive strength and tensile strength of the rock mass described in supporting report 2; repository design and engineering technology of second progress report (H12 report) on research and development for the geological disposal of HLW in Japan.

Diffusion bonding of alumina dispersion-strengthened copper to 316 stainless steel with interlayer metals

Nishi, Hiroshi; Araki, Toshimitsu*; Eto, Motokuni

Fusion Engineering and Design, 39-40, p.505 - 511, 1998/00

https://doi.org/10.1016/S0920-3796(98)00233-6

no abstracts in English

Mechanical tests of diffusion bonding joints o alumina dispersion strengthened copper

Nishi, Hiroshi; Araki, Toshimitsu*

Nihon Genshiryoku Gakkai-Shi, 36(12), p.1134 - 1136, 1994/00

https://doi.org/10.3327/jaesj.36.1134

no abstracts in English

Design of super-heat-resisting structural materials using a d-electron alloy theory (II)

*; Morinaga, Masahiko*; Saito, Junichi*; *; *

PNC TJ9623 92-001, 81 Pages, 1991/07

PNC-TJ9623-92-001.pdf:6.46MB

[PURPOSE] For structural materials serviced in the Li environments, both Nb-based and Mo-based alloys are selected as the candidate materials. In this study, a simple method was proposed for evaluating the high temperature strength of these alloys. Also, the corrosion resistance in liquid metals was investigated in order to get fundamental information for the design and development of high performance alloys. [EXPERIMENTAL AND CALCULATING METHODS] With a variety of ternary alloys high temperature micro-hardness was measured systematically. The results were analyzed by referring to the relationship between the hardness and the tensile strength reported in previous publications. Also, some alloys designed last year were exposed to the liquid Na at 650 C, and the attendant changes were examined with respect to the weight, microstructure and local composition of alloys. Some of the results were understood in terms of the free energy for the oxide formation of Na and other elements in alloys. Another effort to understand the corrosion properties was made by the molecular orbital calculation of the electronic states of various elements in liquid Li, K and Na. [RESULTS] The high temperature tensile strength of both the alloys was found to be predictable by using a linear relationship between the hardness and the tensile strength of room temperature to 1200 C. The corrosion resistance was much poorer in the Nb-based alloys than in the Mo-based alloys. This is partially due to the enhancement of corrosion by the preferred oxidation of Nb and Ta in the Nb-based alloys, whereas no such oxidation took place in the Mo-based alloys. In addition, it was found from the molecular orbital calculation that Li is the liquid metal of more strongly-bonded with every alloying element, compared to K and Na liquid metals. Futhermore, it was shown that the hardness of each alloy correlated well with the atomic-size difference and also the young's modulus difference ...

None

Tsutagi, Koichi; Seki, Masayuki; Tobita, Noriyuki; ; *; *

PNC TN8410 91-174, 40 Pages, 1991/02

PNC-TN8410-91-174.pdf:5.06MB

None

Effects of specimen volume on tensile strength for nuclear-grade

; ;

Tanso, 1985(120), p.45 - 47, 1985/00

https://doi.org/10.7209/tanso.1985.45

no abstracts in English

Evaluations of macro structure and strength of ODS steels heated to ultra-high temperature simulating accident situations

Tanno, Takashi; Fujita, Koji; Yano, Yasuhide; Otsuka, Satoshi; Nakashima, Hideharu*; Mitsuhara, Masatoshi*; Onuma, Masato*; Toyama, Takeshi*; Kaito, Takeji

no journal, , 

By applying oxide dispersion-strengthened (ODS) steel, which has excellent high-temperature strength, to the fuel cladding tube, it is expected that the risk of fuel pin rupture up to the ultra-high temperature range including accidents will be reduced and the safety of the plant will be improved. Oxide dispersoids as a reinforced phase in ODS steels are considered to be more stable than carbonitrides and intermetallic compounds used as reinforced phases in other heat-resistant alloys. It is important to actually ensure that the metallographical structure and strength are maintained up to the ultra-high temperature. In this study, in order to evaluate the performance limit of ODS steel against ultra-high temperature, extreme heat treatments simulating accident situations were carried out, and then the macrostructure and strength were evaluated. Regarding the macrostructure, it was generally stable up to 1250 C and the crystal grains were fine, but it was coarsened at 1300 C or higher. On the other hand, it was found that the hardness decreased at 1250 C or higher. This theme was supported by JPMXD0219214482, a nuclear power system research and development project of the Ministry of Education, Culture, Sports, Science and Technology.