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1.中国科学院上海应用物理研究所 上海 201800
2.中国科学院先进核能创新研究院 上海 201800
LIN Zuokang, male, born in 1984, graduated from University of Chinese Academy of Sciences with a doctoral degree in 2013, focusing on nuclear technology and application
ZHANG Xiaochun, E-mail: zhangxiaochun@sinap.ac.cn
Received:04 July 2019,
Revised:24 July 2019,
Published:13 October 2019
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林作康,王雯,樊辉青等.TMSR-LF1停堆系统高温螺栓连接结构应力松弛分析与结构安全评定[J].核技术,2019,42(10):70-76.
LIN Zuokang,WANG Wen,FAN Huiqing,et al.Analysis and evaluation of stress relaxation for the high temperature bolt connecting structure in scram system of the TMSR-LF1[J].NUCLEAR TECHNIQUES,2019,42(10):70-76.
林作康,王雯,樊辉青等.TMSR-LF1停堆系统高温螺栓连接结构应力松弛分析与结构安全评定[J].核技术,2019,42(10):70-76. DOI: 10.11889/j.0253-3219.2019.hjs.42.100601.
LIN Zuokang,WANG Wen,FAN Huiqing,et al.Analysis and evaluation of stress relaxation for the high temperature bolt connecting structure in scram system of the TMSR-LF1[J].NUCLEAR TECHNIQUES,2019,42(10):70-76. DOI: 10.11889/j.0253-3219.2019.hjs.42.100601.
钍基熔盐液态堆(Thorium Molten Salt Reactor-Liquid Fuel 1,TMSR-LF1)停堆系统螺栓连接结构服役环境约在650 °C的高温区域,连接结构包括三种材质的构件;升温过程热膨胀以及高温下寿期内的蠕变效应,对螺栓的预紧力都有很大影响。本文采用ANSYS程序,对TMSR-LF1停堆系统高温螺栓连接结构,在预紧载荷及热膨胀组合作用下的结构进行了应力分析和寿期内蠕变应力松弛分析。考虑从常温升高至工作温度的过程中,连接结构件由于使用不同材料,其热膨胀差导致预紧力发生变化的过程;着重研究分析运行寿期内螺栓结构材料的高温蠕变,所引起应力松弛的变化规律,及其对螺栓连接结构预紧力的影响;并根据ASME-III-5-HBB规范对螺栓进行力学分析和应力评定,论证该螺栓连接件全寿期内结构安全可靠。
Background
2
The temperature of the bolt connecting structure is around 650 ℃ in the scram system of the thorium molten salt reactor-liquid fuel 1 (TMSR-LF1) and the connecting components include three kinds of material
which have different coefficients of thermal expansion. Thermal expansion during the heating process
from room temperature to 650 ℃
and creep in the long lifetime of reactor will affect the bolt pretension
which may touch the safety of the scram system.
Purpose
2
This study aims to analyse the stress relaxation of the bolting structure
and assess structural safety for the scram system of TMSR-LF1.
Methods
2
The ANSYS program was employed for the mechanical analysis of the bolt connecting model. The stress analysis and creep stress-relaxation analysis of the structure under the combined action of bolting preload and thermal expansion were performed.
Results
2
The high temperature creep of bolted structural materials and the variation of stress relaxation caused by the creep and its influence on the pre-tightening force of bolted connection structures are obtained for the whole lifetime of the reactor. And the evaluation of the bolt is completed under.
Conclusions
2
According to American society of mechanical engineers (ASME) standard in coordinate with ASME-III-5-HBB rules for bolt mechanical analysis and safety evaluation
the connecting bolt structure designed for TMSR-LF1 is demonstrated safe and reliable in the whole lifetime.
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