Design Rules for Nuclear Components in Elevated Temperature

LI Xiao-tian; LUO Xiao-wei; HE Shu-yan

Mar. 2025

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LI Xiao-tian, LUO Xiao-wei, HE Shu-yan. Design Rules for Nuclear Components in Elevated Temperature[J]. Nuclear Power Engineering, 2011, 32(S1): 40-43.

Citation:

LI Xiao-tian, LUO Xiao-wei, HE Shu-yan. Design Rules for Nuclear Components in Elevated Temperature[J]. Nuclear Power Engineering, 2011, 32(S1): 40-43.

LI Xiao-tian, LUO Xiao-wei, HE Shu-yan. Design Rules for Nuclear Components in Elevated Temperature[J]. Nuclear Power Engineering, 2011, 32(S1): 40-43.

Citation:

LI Xiao-tian, LUO Xiao-wei, HE Shu-yan. Design Rules for Nuclear Components in Elevated Temperature[J]. Nuclear Power Engineering, 2011, 32(S1): 40-43.

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Design Rules for Nuclear Components in Elevated Temperature

Institute of Nuclear and New Energy Technology, Tsinghua University, Beijing, 100084, China

Received Date: 2011-01-10
Rev Recd Date: 2011-03-11

Available Online: 2025-03-08

Abstract

Abstract

High-temperature is the common problem for Generation IV reactors.This paper reviews and assesses the currently available codes in the design of high-temperature components,such as ASME-NH,RCC-MR and procedure R5.ASME code is evaluated in-depth by comparing ASME-NB and ASME-NH,Also the application procedures of the ASME-NH rules are described in detail.
- Elevated temperature components,
- Creep-fatigue damage,
- ASME-NH code,
- Evaluation method