期刊论文

中文

核技术 .

Nuclear Techniques

0253-3219

2024

47

10

135-145

10.11889/j.0253-3219.2024.hjs.47.100502

国家自然科学基金(No.52205195)； 湖南省自然科学基金面上项目(No.2023JJ30512)；

本校为第一机构

高温气冷堆中球形燃料元件在往复循环流通过程中存在摩擦磨损问题。采用高能量离子束沉积（Ion Beam Deposition,IBD）镀膜工艺在NBG-18核石墨表面沉积类聚合物碳（Polymer Like Carbon,PLC）涂层，以提升其表面力学与摩擦学性能。镀膜后纳米压痕测试NBG-18核石墨的硬度从0.44 GPa提高到4.16 GPa，提高845%；弹性模量从9.00 GPa提高到27.21 GPa，提高202%；在载荷2 N、滑动频率5 Hz的氮气环境下，TRB3摩擦磨损试验机测试其摩擦系数（Coefficient of Friction,COF）从0.335 7降至0.006 5，降低98%；三维白光干涉仪表征其磨损率从3.71×10-3 mm3·（N·m）-1降至1.81×10-6 mm3·（N·m）-1，降低...

[Background]Nuclear graphite coatings on the surfaces of spherical fuel elements in high-temperature gas-cooled reactors(HTGRs)exhibit a high friction coefficient and low wear resistance.The reciprocating movement of the fuel balls leads to significant friction among the spherical fuel elements and between these elements,the graphite bed,and other components.This friction generates a considerable amount of graphite dust,which poses a risk to the proper functioning of nuclear reactors.[Purpose]This study aims to address the issues of friction an...