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KRUSTY-HEU热管空间堆体积优化及热力耦合特性研究OA北大核心CSTPCD

Study on Volume Optimization and Thermal-mechanical Coupling Characteristics of KRUSTY-HEU Heat Pipe Space Reactor

中文摘要英文摘要

空间热管堆具有小型化、长寿期、环境适应性强等优点,在航天领域中有广阔的应用前景.本文针对由洛斯阿拉莫斯国家实验室提出的高富集度热管空间堆高浓缩铀方案KRUSTY-HEU,在保持反应性不变的前提下,通过添加慢化剂材料的方法进行体积优化,减小控制棒的体积并降低反射层厚度,用以降低航天器的发射成本和发射载荷.在慢化剂布置方面,本文提出了芯块内层添加慢化剂、芯块内部中间层添加慢化剂和慢化剂与燃料弥散3种方案,并对反应性和安全性进行对比.结果表明,芯块内层添加慢化剂方案优于其他两种方案,最低的反射层厚度为8.69 cm,较之前降低了 3.11 cm,体积降低了约30%.针对优化后的方案进行了中子学和热力学分析,结果表明温度对反应性影响较小且移动反射层能够很好地控制反应性,同时燃耗引起的反应性损失较小.在正常运行时,堆芯温度和热位移与之前相差不大,热应力最大处为慢化剂和芯块的交界面,超过了堆芯材料屈服极限.通过在慢化剂和芯块间添加间隙,在材料屈服极限内有效地降低了热应力.单管失效分析表明堆芯温度、位移和热应力发生变化,但未影响其安全性.综上所述,本文提出的芯块内层添加慢化剂方案可有效降低KRUSTY-HEU的体积,热力耦合特性表明优化后的堆芯仍具有较高的安全性和稳定性.

Space heat pipe reactors have the advantages of miniaturization,long life,and strong environmental adaptability,and have broad application prospects in the aerospace field.This study focused on a high-enrichment space heat pipe reactor KRUSTY-HEU proposed by Los Alamos National Laboratory.While maintaining the reactivity,the volume was optimized by adding moderator materials to reduce the control rod's volume and the reflector thickness to decrease spacecraft launch costs and launch loads.In terms of moderator selection,zirconium hydride was selected by comparing the moderator materials commonly used in space reactor with yttrium hydride.For moderator configuration,three schemes including a moderator located inside the core,in the middle,and dispersed in fuel were proposed,and reactivity and safety were analyzed.Three schemes added the same amount of moderator,and the scheme with the largest initial excess reactivity was selected.The results show that the scheme of moderator located inside the core is better than the other two schemes,and the minimum reflector thickness is 8.69 cm,which is 3.11 cm less than before,and the volume is reduced by about 30%.And the reactor remains subcritical state when the control rod is fully inserted and in an unexpected dropping accident.The neutronics and thermal-mechanics were carried out for the optimized scheme.The results show that the fuel temperature has little influence on the reactivity,besides the reactivity do not change with the change of moderator temperature.Moving reflector can control the reactivity effectively,the differential value of the reflector control is highest when the radial reflector moves about 20 cm.The reactivity caused by burnup is small,when the reactor runs for 15 years,the reactivity is basically unchanged,due to the low power of 4.3 kW.During normal operation,the core temperature and thermal displacement are not much different from before,and the maximum thermal stress is about 200 MPa at the interface of moderator and core,which exceeds the yield limit of core material.The thermal stress is effectively reduced to about 63.3 MPa within the yield limit of the material by adding a gap between the moderator and the core.Single pipe failure analysis shows that core temperature,displacement and thermal stress have changed,but it do not affect its safety.In summary,the moderator located inside the core scheme proposed in this study can effectively reduce the volume of KRUSTY-HEU,and the thermal-mechanical coupling characteristics show that the optimized core still has high safety and stability.

张开辉;庄坤;张欣欣;王森山;邓丽娜;王永战;王莹桢

南京航空航天大学,江苏南京 210000

核科学

空间堆KRUSTYHEU中子物理学热力耦合分析

space reactorKRUSTYHEUneutron physicsthermal-mechanical coupling

《原子能科学技术》 2024 (006)

1250-1260 / 11

国家自然科学基金青年基金(12205150);江苏省自然科学基金青年基金(BK20210304);中国博士后基金站前特别资助项目(2019TQ0148)

10.7538/yzk.2023.youxian.0790

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