scholarly journals IN-PILE LOOP IRRADIATION OF AQUEOUS THORIA-URANIA SLURRY AT ELEVATED TEMPERATURE. DESIGN AND IN-PILE OPERATION OF LOOP L-2-27S

1962 ◽  
Author(s):  
H.C. Savage ◽  
E.L. Compere ◽  
J.M. Baker ◽  
V.A. DeCarlo ◽  
A.J. Shor
Keyword(s):  
Elevated Temperature ◽  
Elevated Temperature Design ◽  
Pile Operation

Elastic Allowable Stress Basis for Elevated Temperature Design in the Creep Regime

2016 ◽  
Author(s):  
Chithranjan Nadarajah ◽  
Benjamin F. Hantz ◽  
Sujay Krishnamurthy
Keyword(s):  
Finite Element ◽  
Elevated Temperature ◽  
Pressure Vessel ◽  
Reasonable Agreement ◽  
Allowable Stress ◽  
Elastic Stresses ◽  
Finite Element Stress Analysis ◽  
Section Viii ◽  
Elevated Temperature Design ◽  
Creep Regime

ASME Section VIII, Division II, Boiler and Pressure Vessel Code does not have any design by analysis procedures for designing pressure vessel components in the creep regime. This publication presents a methodology for evaluating and categorizing elastic stresses calculated from finite element stress analysis when designing in the creep regime. The proposed methodology is compared with multi axial creep results for various pressure vessel components and found to be in reasonable agreement.

Development of the External Pressure Charts for 2¼Cr-1Mo and Mod.9Cr-1Mo Steel at Elevated Temperature Design

2019 ◽  
Author(s):  
Masanori Ando ◽  
Satoshi Okajima ◽  
Kazumichi Imo
Keyword(s):  
Elevated Temperature ◽  
Fast Reactor ◽  
Strain Curve ◽  
External Pressure ◽  
Stress Strain ◽  
Part D ◽  
Elevated Temperature Design ◽  
Minimum Stress ◽  
Design Yield ◽  
Strain Equation

Abstract For the required thickness estimation against buckling in the elevated temperature design, the external pressure chart for two kinds of ferritic steel, 2 1/4Cr-1Mo and Mod.9Cr-1Mo steel, was developed. On the basis of the guideline described in the ASME BPVC Section II, Part D, Mandatory Appendix 3 with mechanical and physical properties provided in the JSME fast reactor code, the external pressure charts for each material were constructed. The minimum stress-strain curve for evaluating the external pressure chart was applied the stress-strain equation with design yield strength, Sy, provided by the JSME fast reactor code. As a result, three external pressure charts with digital values were proposed for elevated temperature design. Moreover, the rationalization effect from the current alternative was evaluated by the sample problem. This proposal resolves two issues. One is alternative use of chart for lower strength material over the 150 °C. The other is the external pressure chart above 480°C for which ferritic steels are not available.

Grade 11 High Temperature Steam Header Case History and Benchmark

2016 ◽  
Author(s):  
Dave Dewees
Keyword(s):  
High Temperature ◽  
Elevated Temperature ◽  
Method Validation ◽  
Case History ◽  
Design Method ◽  
Fatigue Behavior ◽  
Method Performance ◽  
Elevated Temperature Design ◽  
High Temperature Steam ◽  
Grade 11

The cost and complexity of design method validation at the component level makes actual and comprehensive benchmark cases challenging to obtain. This is especially true of elevated temperature design methods where component and material response is complicated by time-dependent creep and possibly creep-fatigue behavior. To support current Design-by-Analysis modernization development within Section I of the ASME Boiler & Pressure Vessel Code, service examples that are comprehensive enough to allow method validation, while still being tractable in complexity have been identified. To this end, the case history of a Grade 11 high temperature steam outlet header that was retired after 23 of years of service is presented. Detailed damage and deformation information is available which allows validation of creep material models, as well as future evaluation of candidate elevated temperature design method performance.

On a Design Acceptability of 90° Elbow According to Pipe Length at Elevated Temperature Condition

2016 ◽  
Author(s):  
Seong-Yun Jeong ◽  
Min-Gu Won ◽  
Jae-Boong Choi ◽  
Nam-Su Huh ◽  
Young-Jin Oh
Keyword(s):  
Elevated Temperature ◽  
Structural Integrity ◽  
Seismic Damage ◽  
Design Codes ◽  
Finite Element Analyses ◽  
Promising Candidate ◽  
Pipe Length ◽  
Integrity Assessment ◽  
Creep Fatigue ◽  
Elevated Temperature Design

Sodium-cooled Fast Reactor, SFR is promising candidate of Generation-IV reactor. SFR is operated at high temperature and low pressure. For reducing high thermal stress, thin-walled components and structures are employed for SFR. However, thins-walled components are vulnerable to seismic damage[1]. In this paper, the structural integrity assessment are performed to investigate the effect of piping length on creep-fatigue and seismic damage at elevated temperature. L-shaped elbow is considered for piping design and finite element analyses are conducted to calculate creep-fatigue and seismic damage. The evaluation of creep fatigue damage is carried out according to the elevated temperature design codes of ASME B&PV Sec. III Subsec. NH-3200[2]. Seismic damage are evaluated based ASME B&PV Sec. III Subsec. NB-3600[3] and ASME B&PV Sec. III Div.5 HBB-3200[4]. From the results of creep-fatigue and seismic damage, limit length of piping is determined.

scholarly journals Inelastic Material Models of Type 316H for Elevated Temperature Design of Advanced High Temperature Reactors

Energies ◽  
2020 ◽  
Vol 13 (17) ◽  
pp. 4548
Author(s):  
Gyeong-Hoi Koo ◽  
Ji-Hyun Yoon
Keyword(s):  
High Temperature ◽  
Elevated Temperature ◽  
Constitutive Equations ◽  
Isotropic Hardening ◽  
Material Models ◽  
Material Parameters ◽  
Hardening Behavior ◽  
Inelastic Material ◽  
High Temperature Reactors ◽  
Elevated Temperature Design

In this paper, the inelastic material models for Type 316H stainless steel, which is one of the principal candidate materials for elevated temperature design of the advanced high temperature reactors (HTRs) pressure retained components, are investigated and the required material parameters are identified to be used for both elasto-plastic models and unified viscoplastic models. In the constitutive equations of the inelastic material models, the kinematic hardening behavior is expressed with the Chaboche model with three backstresses, and the isotropic hardening behavior is expressed by the Voce model. The required number of material parameters is minimized to be ten in total. For the unified viscoplastic model, which can express both the time-independent plastic behavior and the time-dependent viscous behavior, the constitutive equations have the same kinematic and isotropic hardening parameters of the elasto-plastic material model with two additional viscous parameters. To identify the material parameters required for these constitutive equations, various uniaxial tests were carried out at isothermal conditions at room temperature and an elevated temperature range of 425–650 °C. The identified inelastic material parameters were validated through the comparison between tests and calculations.

Proposal for the Implementation of Elevated Temperature Design Fatigue Curve for 2-1/4Cr-1Mo-V and 3Cr-1Mo-V Steels

2004 ◽  
Author(s):  
Tatsumi Takehana ◽  
Takeru Sano ◽  
Susumu Terada ◽  
Hideo Kobayashi
Keyword(s):  
Elevated Temperature ◽  
Fatigue Strength ◽  
High Strength ◽  
Fatigue Curve ◽  
Temperature Limit ◽  
Fatigue Tests ◽  
Low Alloy Steels ◽  
Alloy Steels ◽  
Elevated Temperature Design

2-1/4Cr-1Mo-V and 3Cr-1Mo-V steels have been used extensively as materials for elevated temperature and high-pressure hydro-processing reactors. These steels have both of high strength at elevated temperature and high resistance against elevated temperature hydrogen attack due to the addition of vanadium. The operating temperature of these reactors is between 800 and 900deg.F. The fatigue evaluations of these reactors per ASME Sec. VIII Div.2 and Div.3 can’t be performed in spite of demand for fatigue analysis because the temperature limit of design fatigue curve in ASME Sec. VIII Div.2 and Div.3 for carbon and low alloy steels is 700deg.F. Results of load and strain controlled fatigue tests conducted over the temperature range from room temperature to 932deg.F (500deg.C) are reported for 2-1/4Cr-1Mo-V and 3Cr-1Mo-V steels. These data were compared with data for 2-1/4Cr-1Mo steels available from the literatures. The fatigue strength for a 2-1/4Cr-1Mo-V steel in high cycle region is higher than that for 2-1/4Cr-1Mo steels and in low cycle region is lower. The fatigue strength for a 3Cr-1Mo-V steel is almost same as that for 2-1/4Cr-1Mo-V steels. Therefore an elevated temperature design fatigue curve for 2-1/4Cr-1Mo-V and 3Cr-1Mo-V steels is newly proposed. It is found from the case study that the different fatigue life can be predicted by using different mean stress correction procedure.

Design Criteria for Boilers and Pressure Vessels in the U.S.A.

1988 ◽  
Vol 110 (4) ◽  
pp. 430-443 ◽  
Author(s):  
Martin D. Bernstein
Keyword(s):  
Elevated Temperature ◽  
Pressure Vessel ◽  
Failure Modes ◽  
Pressure Vessels ◽  
Design Criteria ◽  
The Future ◽  
Recent Developments ◽  
Design Loads ◽  
Elevated Temperature Design

Preface. Code criteria defined. Evolution of ASME Boiler and Pressure Vessel Code. How the Code operates today. Design by rule. Evolution of design by analysis. Types of stress and their significance. Failure modes. Strength theories. Design loads. New or unusual designs. Code Cases. Interpretations. Stress limits for design by rule and design by analysis. Elevated temperature design. Recent developments. A glimpse at the future. References.

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