{"title":"Thermal fatigue tests of a prototype beryllium limiter for jet","authors":"R.D. Watson,&nbsp;J.B. Whitley","doi":"10.1016/0167-899X(86)90011-X","DOIUrl":null,"url":null,"abstract":"<div><p>Beryllium is an attractive alternative to graphite for use as armor material for plasma interactive components in fusion devices because of its low atomic number, high strength, and good compatibility with hydrogen. However, beryllium is susceptible to damage from cyclic thermal stresses because of its high elastic modulus and thermal expansion coefficient. We have performed 2-D elastic-plastic finite element stress analyses of prototype beryllium limiter tiles for the JET project that are exposed to a surface heat flux of 250 W/cm<sup>2</sup> for 15 second pulses. Plastic deformation was predicted to occur at the heated surface during both the heating and cooling phases of the cycle, thereby causing cyclic plastic strain. We also performed thermal fatigue tests using a rastered electron beam to apply the heat load to prototype limiter specimens. After 10 000 thermal fatigue cycles, the only damage of the beryllium tile was microcracking of the heated surface. The depth of this microcracking, 4 mm, corresponds closely to the calculated depth of cyclic plastic strain. These favorable results show that the operating conditions for the JET limiter design can be extended into the regime of cyclic plastic deformation without causing overall structural failure, despite the formation of thermal fatigue cracks.</p></div>","PeriodicalId":82205,"journal":{"name":"Nuclear engineering and design/fusion : an international journal devoted to the thermal, mechanical, materials, structural, and design problems of fusion energy","volume":"4 1","pages":"Pages 49-60"},"PeriodicalIF":0.0000,"publicationDate":"1986-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1016/0167-899X(86)90011-X","citationCount":"25","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Nuclear engineering and design/fusion : an international journal devoted to the thermal, mechanical, materials, structural, and design problems of fusion energy","FirstCategoryId":"1085","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/0167899X8690011X","RegionNum":0,"RegionCategory":null,"ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"","JCRName":"","Score":null,"Total":0}
引用次数: 25

Abstract

Beryllium is an attractive alternative to graphite for use as armor material for plasma interactive components in fusion devices because of its low atomic number, high strength, and good compatibility with hydrogen. However, beryllium is susceptible to damage from cyclic thermal stresses because of its high elastic modulus and thermal expansion coefficient. We have performed 2-D elastic-plastic finite element stress analyses of prototype beryllium limiter tiles for the JET project that are exposed to a surface heat flux of 250 W/cm2 for 15 second pulses. Plastic deformation was predicted to occur at the heated surface during both the heating and cooling phases of the cycle, thereby causing cyclic plastic strain. We also performed thermal fatigue tests using a rastered electron beam to apply the heat load to prototype limiter specimens. After 10 000 thermal fatigue cycles, the only damage of the beryllium tile was microcracking of the heated surface. The depth of this microcracking, 4 mm, corresponds closely to the calculated depth of cyclic plastic strain. These favorable results show that the operating conditions for the JET limiter design can be extended into the regime of cyclic plastic deformation without causing overall structural failure, despite the formation of thermal fatigue cracks.

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喷射用铍限制器原型的热疲劳试验
铍具有原子序数低、强度高、与氢的相容性好等优点,是石墨在聚变装置中等离子体相互作用部件装甲材料中的一个有吸引力的替代品。然而,铍具有较高的弹性模量和热膨胀系数,容易受到循环热应力的破坏。我们对JET项目的原型铍限制瓦进行了二维弹塑性有限元应力分析,该原型暴露在250 W/cm2的表面热通量下,脉冲时间为15秒。预测在循环的加热和冷却阶段,被加热表面都会发生塑性变形,从而引起循环塑性应变。我们还使用光栅电子束进行热疲劳测试,将热负荷应用于原型限制器样品。经过10000次热疲劳循环后,铍瓦唯一的损伤是受热表面的微裂纹。微裂纹的深度为4mm,与循环塑性应变的计算深度非常接近。这些良好的结果表明,JET限位器设计的工作条件可以扩展到循环塑性变形状态,而不会导致整体结构破坏,尽管会形成热疲劳裂纹。
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Preface Announcement Cryopumping for fusion reactors 2.1. Development of low activation Al alloys for the R-project 6. Research and development on the tritium handling technology in the R-project
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