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High temperature structural integrity evaluation method and application studies by ASME-NH for the next generation reactor design

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Abstract

The main purpose of this paper is to establish the high temperature structural integrity evaluating procedures for the next generation reactors, which are to be operated at over 500°C and for 60 years. To do this, comparison studies of the high temperature structural design codes and assessment procedures such as the ASME-NH (USA), RCC-MR (France), DDS (Japan), and R5 (UK) are carried out in view of the accumulated inelastic strain and the creep-fatigue damage evaluations. Also the application procedures of the ASME-NH rules with the actual thermal and structural analysis results are described in detail. To overcome the complexity and the engineering costs arising from a real application of the ASME-NH rules by hand, all the procedures established in this study such as the time-dependent primary stress limits, total accumulated creep ratcheting strain limits, and the creep-fatigue damage limits are computerized and implemented into the SIE ASME-NH program. Using this program, the selected high temperature structures subjected to two cycle types are evaluated and the parametric studies for the effects of the time step size, primary load, number of cycles, normal temperature for the creep damage evaluations and the effects of the load history on the creep ratcheting strain calculations are investigated.

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Abbreviations

j:

j-th cycle type

Kt :

Bending stress reduction factor due to creep

Kε, K’e :

Strain concentration factor

K, KL, KT :

Stress concentration factor

Kv :

Multiaxial plasticity and Poisson ratio adjustment factor

N:

Number of cycle type

P1 :

Effective primary membrane stress intensity

P3 :

Effective primary stress intensity with creep effect

Pb :

Primary bending stress intensity

PL :

Local primary membrane stress intensity

Pm :

Primary membrane stress intensity

(QR) max:

The maximum range of the secondary stress intensity

S*,S :

Stress indicators

Sy :

Averaged yield stress for the max. and the min. temp.

Sa :

Min [1.25St¦Tmax,104hr, averaged Sy]

t:

Time

T:

Temperature

V:

Efficiency index

X, Y:

Stress parameters

εp :

Plastic strain

εc :

Creep strain

εec :

Enhanced creep strain

εmR :

Ratchet strain (membrane)

εbR :

Ratchet strain (bending)

εmEF :

Elastic followup strain by long term secondary bending stress (membrane)

εbEF :

Elastic followup strain by long term secondary bending stress (bending)

εt :

Total strain range

σb :

Corrected primary bending stress intensity

σc :

Effective creep stress

σL :

Corrected local primary membrane stress intensity

σm :

Corrected primary membrane stress intensity

Φ:

Bending stress reduction factor due to creep

References

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Authors and Affiliations

  1. Mechanical Engineering Division, LMR Structural Design Development, Korea Atomic Energy Research Institute, P.O.Box 105, 305-600, Yusung, Daejeon, Korea

    Gyeong-Hoi Koo & Jae-Han Lee

Authors
  1. Gyeong-Hoi Koo
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  2. Jae-Han Lee
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Correspondence to Gyeong-Hoi Koo.

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Koo, GH., Lee, JH. High temperature structural integrity evaluation method and application studies by ASME-NH for the next generation reactor design. J Mech Sci Technol 20, 2061–2078 (2006). https://doi.org/10.1007/BF02916323

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  • DOI: https://doi.org/10.1007/BF02916323

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