scholarly journals High Temperature Strength. Development of Long Term Creep-Fatigue Evaluation Method for Stainless Steel Weldments, II. Evaluation of Long-Term Creep-Fatigue Life of Stainless Steel Weldment Based on a Microstructure Degradation Model.

1997 ◽  
Vol 46 (1) ◽  
pp. 65-69
Author(s):  
Tai ASAYAMA ◽  
Shinichi HASEBE
Keyword(s):  
Stainless Steel ◽  
Evaluation Method ◽  
Strength Development ◽  
High Temperature Strength ◽  
Degradation Model ◽  
Creep Fatigue ◽  
Stainless Steel Weldment ◽  
Fatigue Evaluation ◽  
Term Creep

Development of Creep–Fatigue Evaluation Method for 316FR Stainless Steel

2015 ◽  
Vol 137 (4) ◽  
Author(s):  
Yuji Nagae ◽  
Shigeru Takaya ◽  
Tai Asayama
Keyword(s):  
Stainless Steel ◽  
Fatigue Life ◽  
Evaluation Method ◽  
Elevated Temperatures ◽  
Strain Curve ◽  
Creep Damage ◽  
Fatigue Curve ◽  
Time To Failure ◽  
Creep Fatigue ◽  
Fatigue Evaluation

In the design of fast reactor plants, the most important failure mode to be prevented is creep–fatigue damage at elevated temperatures. 316FR stainless steel is a candidate material for the reactor vessel and internal structures of such plants. The development of a procedure for evaluating creep–fatigue life is essential. The method for evaluating creep–fatigue life implemented in the Japan Society of Mechanical Engineers code is based on the time fraction rule for evaluating creep damage. Equations such as the fatigue curve, dynamic stress–strain curve, creep rupture curve, and creep strain curve are necessary for calculating creep–fatigue life. These equations are provided in this paper and the predicted creep–fatigue life for 316FR stainless steel is compared with experimental data. For the evaluation of creep–fatigue life, the longest time to failure is about 100,000 h. The creep–fatigue life is predicted to an accuracy that is within a factor of 2 even in the case with the longest time to failure. Furthermore, the proposed method is compared with the ductility exhaustion method to investigate whether the proposed method gives conservative predictions. Finally, a procedure based on the time fraction rule for the evaluation of creep–fatigue life is proposed for 316FR stainless steel.

scholarly journals Evaluation of Long Term Creep-Fatigue Life for Type 304 Stainless Steel.

1992 ◽  
Vol 41 (471) ◽  
pp. 1773-1778 ◽  
Author(s):  
Hirotsugu KAWASAKI ◽  
Fumiyoshi UENO ◽  
Kazumi AOTO ◽  
Masakazu ICHIMIYA ◽  
Yusaku WADA
Keyword(s):  
Stainless Steel ◽  
Fatigue Life ◽  
304 Stainless Steel ◽  
Creep Fatigue ◽  
Term Creep ◽  
Type 304 ◽  
Type 304 Stainless Steel

Development of 2012 Edition of JSME Code for Design and Construction of Fast Reactors: (4) Creep–Fatigue Evaluation Method for Modified 9Cr–1Mo Steel

2013 ◽  
Author(s):  
Shigeru Takaya ◽  
Yuji Nagae ◽  
Tai Asayama
Keyword(s):  
Evaluation Method ◽  
Time To Failure ◽  
Test Results ◽  
Fast Reactors ◽  
Material Test ◽  
Creep Fatigue ◽  
Summation Rule ◽  
Fatigue Evaluation ◽  
Failure Life ◽  
Design And Construction

This paper describes a creep–fatigue evaluation method for modified 9Cr–1Mo steel, which has been newly included in the 2012 edition of the JSME code for design and construction of fast reactors. In this method, creep and fatigue damages are evaluated on the basis of Miner’s rule and the time fraction rule, respectively, and the linear summation rule is employed as the failure criterion. Investigations using material test results are conducted, which show that the time fraction approach can conservatively predict failure life if margins on the initial stress of relaxation and the stress relaxation rate are embedded. In addition, the conservatism of prediction tends to increase with time to failure. Comparison with the modified ductility exhaustion method, which is known to have good failure life predictability in material test results, shows that the time fraction approach predicts failure lives to be shorter in long-term strain hold conditions, where material test data is hardly obtained. These results confirm that the creep–fatigue evaluation method in the code has implicit conservatism.

scholarly journals Elevated-Temperature Mechanical Properties of an Advanced-Type 316 Stainless Steel1

2000 ◽  
Vol 123 (1) ◽  
pp. 75-80 ◽  
Author(s):  
Charles R. Brinkman
Keyword(s):  
Mechanical Properties ◽  
Stainless Steel ◽  
Elevated Temperature ◽  
National Laboratory ◽  
Low Carbon ◽  
Oak Ridge ◽  
Creep Fatigue ◽  
Nippon Steel Corporation ◽  
Term Creep ◽  
Product Forms

Type 316FR stainless steel is a candidate material for the Japanese demonstration fast breeder reactor plant to be built in Japan early in the next century. Like type 316L(N), it is a low-carbon grade of stainless steel with a more closely specified nitrogen content and chemistry optimized to enhance elevated-temperature performance. Early in 1994, under sponsorship of The Japan Atomic Power Company, work was initiated at Oak Ridge National Laboratory (ORNL) aimed at obtaining an elevated-temperature mechanical-properties database on a single heat of this material. The product form was 50-mm plate manufactured by the Nippon Steel Corporation. Data include results from long-term creep-rupture tests conducted at temperatures of 500 to 600°C with test times up to nearly 40.000 h, continuous-cycle strain-controlled fatigue test results over the same temperature range, limited creep-fatigue data at 550 and 600°C, and tensile test properties from room temperature to 650°C. The ORNL data were compared with data obtained from several different heats and product forms of this material obtained at Japanese laboratories. The data were also compared with results from predictive equations developed for this material and with data available for types 316 and 316L(N) stainless steel.

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