V型凹口对液态熔盐堆用核石墨构件应力分析的影响

杨雄; 曾广礼; 顾晨光; 钟阳; 丁冬

doi:10.11889/j.0253-3219.2017.hjs.40.070601

您当前的位置：

首页 >

文章列表页 >

V型凹口对液态熔盐堆用核石墨构件应力分析的影响

核能科学与工程 | 更新时间：2021-05-19

- V型凹口对液态熔盐堆用核石墨构件应力分析的影响
  封面论文
- Effect of V shape notch on stress analysis of nuclear graphite component for liquid molten salt reactor
- 核技术 2017年40卷第7期文章编号：070601
- 作者机构：
  
  1.中国科学院上海应用物理研究所嘉定园区上海 201800
  2.中国科学院大学北京 100049
- 作者简介：
  
  [ "杨雄, 女, 1989年出生, 2013年毕业于南华大学, 现为博士研究生, 研究领域为核石墨应力分析" ]
  曾广礼, E-mail:zengguangli@sinap.ac.cn ZENG Guangli, E-mail:zengguangli@sinap.ac.cn
- 基金信息：
  
  人力资源和社会保障部课题(Y419016031)
- DOI：10.11889/j.0253-3219.2017.hjs.40.070601
  中图分类号： TL99
- 收稿日期：2017-02-27，
  
  修回日期：2017-04-19，
  
  纸质出版日期：2017-07-10
- 稿件说明：
移动端阅览
杨雄, 曾广礼, 顾晨光, 等. V型凹口对液态熔盐堆用核石墨构件应力分析的影响[J]. 核技术, 2017,40(7):070601

Xiong YANG, Guangli ZENG, Chenguang GU, et al. Effect of V shape notch on stress analysis of nuclear graphite component for liquid molten salt reactor[J]. Nuclear techniques, 2017, 40(7): 070601
杨雄, 曾广礼, 顾晨光, 等. V型凹口对液态熔盐堆用核石墨构件应力分析的影响[J]. 核技术, 2017,40(7):070601 DOI： 10.11889/j.0253-3219.2017.hjs.40.070601.

Xiong YANG, Guangli ZENG, Chenguang GU, et al. Effect of V shape notch on stress analysis of nuclear graphite component for liquid molten salt reactor[J]. Nuclear techniques, 2017, 40(7): 070601 DOI： 10.11889/j.0253-3219.2017.hjs.40.070601.

摘要

本文利用了一个根据球床模块堆（Pebble Bed Modular Reactor

PBMR）用核石墨材料辐照性能数据编写的用户自定义材料模型（User defined Material model

UMAT），按照美国橡树岭国家实验室（Oak Ridge National Laboratory

ORNL）的液态燃料熔盐试验堆（Molten Salt Reactor Experiment

MSRE）用核石墨构件尺寸，为钍基熔盐堆（Thorium-based Molten Salt Reactor

TMSR）设计了一款方型核石墨构件。利用新编UMAT对该核石墨构件进行了初步的应力分析。分析结果表明，在没有预制裂纹的情况下辐照梯度越大核石墨构件中心区域最大主应力值越大，构件的断裂位置可能出现在构件中心位置处；对于有V型凹口预制裂纹的情况，应力集中部位均出现在预制裂纹尖端附近，这将可能导致裂纹尖端附近出现裂纹扩展，从而引起构件断裂失效。

Abstract

Background

Nuclear graphite has served as neutron moderator

reflector and structural material in the liquid molten salt reactor (MSR) due to its excellent irradiation performance and mechanical properties at high temperature. During the life time of reactors

the properties of nuclear graphite will be changed due to the irradiation damage.

Purpose

The aim is to study the effect of V-shape notch on stress analysis of nuclear graphite component for liquid MSR.

Methods

A user-defined material model (UMAT) was used to model the irradiation behavior of nuclear graphite component. The finite element method was used to develop numerical models for the stress analysis of nuclear graphite component.

Results and Conclusion

The stress of nuclear graphite component increases as the irradiation gradient. What's more

the stress results of nuclear graphite component without crack and with V-shape crack are different. In the absence of a V-shape crack

the fracture position of the square-shaped graphite component may occur at the center of the structure. In the case of having a V-shape crack

the crack propagation may occur near the crack tip of the nuclear graphite component

which may cause fracture failure of the component.

关键词

Keywords

references

Forsberg C W, Snead L L, Katoh Y. Fluoride-salt-cooled high-temperature reactor (FHR) with silicon-carbide-matrix coated-particle fuel[A]. Transactions of the American Nuclear Society[C]. American Nuclear Society Winter Meeting, San Diego, CA, New York: Academic Press, 2012: 907-910.

Greene S R, Gehin J C, Holcomb D E, et al. Pre-conceptual design of a fluoride-salt-cooled small modular advanced high temperature reactor (SmAHTR)[R]. United States: Oak Ridge National Laboratory, 2011. DOI: 10.2172/1008830. http://dx.doi.org/10.2172/1008830.

K Furukawa , L B Erbay , A Aykol . A study on a symbiotic thorium breeding fuel-cycle: THORIMS-NES through FUJI . Energy Conversion & Management , 2012 . 63 ( 6 ): 51 - 54 . DOI: 10.1016/j.enconman.2012.01.030 http://doi.org/10.1016/j.enconman.2012.01.030 .

Z He , L Gao , W Qi . Molten FLiNaK salt infiltration into degassed nuclear graphite under inert gas pressure . Carbon , 2015 . 84 ( 1 ): 511 - 518 . DOI: 10.1016/j.carbon.2014.12.044 http://doi.org/10.1016/j.carbon.2014.12.044 .

S Jing , C Zhang , J Pu , . 3D microstructures of nuclear graphite: IG-110, NBG-18 and NG-CT-10 . Nuclear Science and Techniques , 2016 . 27 ( 3 ): 66 DOI: 10.1007/s41365-016-0071-0 http://doi.org/10.1007/s41365-016-0071-0 .

P N Haubenreich , J R Engel . Experience with the molten-salt reactor experiment . Nuclear Applications & Technology , 1970 . 8 ( 2 ): 118 - 136 . DOI: 10.13182/NT8-2-118 http://doi.org/10.13182/NT8-2-118 .

Bodel W. The relationship between microstructure and young's modulus of nuclear graphite[D]. UK: The University of Manchester, 2013.

D K L Tsang , B J Marsden . Constitutive material model for the prediction of stresses in irradiated anisotropic graphite components . Journal of Nuclear Materials , 2008 . 381 ( 1-2 ): 129 - 136 . DOI: 10.1016/j.jnucmat.2008.07.025 http://doi.org/10.1016/j.jnucmat.2008.07.025 .

D K L Tsang , B J Marsden . The development of a stress analysis code for nuclear graphite components in gras-cooled reactors . Journal of Nuclear Materials , 2006 . 350 ( 3 ): 208 - 220 . DOI: 10.1016/j.jnucmat.2006.01.015 http://doi.org/10.1016/j.jnucmat.2006.01.015 .

B R Lawn . Fracture of brittle solids , : 2nd ed. Cambridge Cambridge University Press , 1993 . DOI: 10.1017/CBO9780511623127 http://doi.org/10.1017/CBO9780511623127 .

D K L Tsang , B J Marsden . Effects of dimensional change strain in nuclear graphite component stress analysis . Nuclear Engineering & Design , 2007 . 237 ( 9 ): 897 - 904 . DOI: 10.1016/j.nucengdes.2006.01.015 http://doi.org/10.1016/j.nucengdes.2006.01.015 .

D K L Tsang , B J Marsden , J A Vreeling , . Analyses of a restrained growth graphite irradiation creep experiment . Nuclear Engineering & Design , 2008 . 238 ( 11 ): 3026 - 3030 . DOI: 10.1016/j.nucengdes.2007.12.017 http://doi.org/10.1016/j.nucengdes.2007.12.017 .

Luyken L. Using intercalation to simulate irradiation damage of nuclear graphite[D]. UK: The University of Manchester, 2012.

B E Mironov , H M Freeman , A P Brown , . Electron irradiation of nuclear graphite studied by transmission electron microscopy and electron energy loss spectroscopy . Carbon , 2015 . 83 106 - 117 . DOI: 10.1016/j.carbon.2014.11.019 http://doi.org/10.1016/j.carbon.2014.11.019 .

G Hall , B J Marsden , J Smart , . Finite-element modelling of nuclear-grade graphite . Nuclear Energy , 2002 . 41 ( 1 ): 53 - 62 . DOI: 10.1680/nuen.41.1.53.39011 http://doi.org/10.1680/nuen.41.1.53.39011 .

C E Inglis . Stress distribution in a rectangular plate having two opposing edges sheared in opposite directions . Proceedings of the Royal Society of London , 1923 . 103 ( 723 ): 598 - 610 . DOI: 10.1098/rspa.1923.0081 http://doi.org/10.1098/rspa.1923.0081 .

浏览量

下载量

CSCD

文章被引用时，请邮件提醒。

提交

工具集

关联资源

氮气环境下NBG-18核石墨表面类聚合物碳涂层的摩擦学性能研究

金属镍、铁和钨初级辐照损伤演化的分子动力学研究

间隙原子在核石墨中迁移与结合规律的模拟计算

双极线性稳压器中子辐射位移效应研究

基于ASME规范的核石墨改进概率评价方法研究