Comparison and Assessment of the Creep-Fatigue Evaluation Methods With Notched Specimen Made of Mod.9Cr-1Mo Steel

Author:

Ando Masanori1,Hirose Yuichi2,Karato Takanori3,Watanabe Sota4,Inoue Osamu5,Kawasaki Nobuchika1,Enuma Yasuhiro6

Affiliation:

1. Japan Atomic Energy Agency, 4002 Narita, Oarai, Ibaraki 311-1393, Japan

2. Mitsubishi Heavy Industry, Ltd., 5-717-1 Fukahori, Nagasaki, Nagasaki 851-0392, Japan

3. Mitsubishi Heavy Industry, Ltd., 2-1-1 Shinhama, Arai, Takasago, Hyogo 676-8686, Japan

4. Mitsubishi Heavy Industry, Ltd., 1-1-1 Wadamisaki, Hyogo, Kobe, Hyogo 652-8585, Japan

5. IX Knowledge, Inc., 4002 Narita, Oarai, Ibaraki 311-1393, Japan

6. Mitsubishi FBR Systems, Inc., 2-34-17, Jingumae, Shibuya, Tokyo 150-0001, Japan

Abstract

In components design at elevated temperature, creep-fatigue is one of the most important failure modes, and assessment of creep-fatigue life in structural discontinuities is an important issue in evaluating the integrity of components. Therefore, a lot of creep-fatigue life evaluation methods were proposed until now. To compare and assess the evaluation methods, a series of creep-fatigue test was carried out with notched specimens. All the specimens were made of Mod.9Cr-1Mo steel, which is a candidate material for primary and secondary heat transport system components of the Japan sodium-cooled fast reactor (JSFR). Mechanical creep-fatigue tests and thermal creep-fatigue test were performed by using a conventional uni-axial push–pull fatigue test machine and a thermal gradient generating system with an induction heating. The stress concentration levels were adjusted by varying the notch radius in the each test. The creep-fatigue lives, crack initiation, and propagation processes were monitored by a digital microscope and the replica method. A series of finite element analysis (FEA) was carried out to predict the number of cycles to failure by the several creep-fatigue life evaluation methods. Then, these predictions were compared with the test results. Several types of evaluation methods such are stress redistribution locus (SRL) method, simple elastic follow-up method and the methods described in the design and constriction code for fast reactor (FR) published by the Japan Society of Mechanical Engineers (JSME FRs code) were applied. Through the comparisons, it was appeared that SRL method gave rational conservative prediction of the creep-fatigue life when the factor of κ = 1.6 was applied for all conditions tested in this study. A comparison of SRL method and simple elastic follow-up method indicated that SRL method applied factor of κ = 1.6 gave the smallest creep-fatigue life in practicable stress range level. The JSME FRs code gave an evaluation 70–100 times conservative lives comparing with the test results.

Publisher

ASME International

Subject

Mechanical Engineering,Mechanics of Materials,Safety, Risk, Reliability and Quality

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