薄壁管高温爆破试验装置研制及应用

韩志博; 杨洪广; 张建通

doi:10.7538/yzk.2019.youxian.0611

薄壁管高温爆破试验装置研制及应用

中国原子能科学研究院反应堆工程技术研究部,北京102413

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出版历程
- 刊出日期: 2020-04-19

Development and Application of High Temperature Burst Facility of Thin-walled Tube

Division of Reactor Engineering Technology Research, China Institute of Atomic Energy, Beijing 102413, China

摘要

摘要: 为获得燃料组件及燃料相关组件用包壳管的高温爆破性能，研制了薄壁金属管高温爆破试验装置，主要由高压气源单元、试验气氛单元、加热单元、试验台架及测控单元组成。该装置可实现的最高试验温度为1 200 ℃、最高升温速率为10 ℃/s、最大试验压力为100 MPa；可完成压水堆运行工况下的等温高温爆破及模拟事故工况下的瞬态加热高温爆破两种试验。利用该装置完成了316L不锈钢薄壁管的瞬态加热高温爆破试验，获得了600~1 200 ℃、升温速率为5 ℃/s条件下的高温爆破强度（极限环向应力）和周向延伸率数据。试验装置的验证及不锈钢薄壁管的高温爆破试验表明，研制的薄壁金属管高温爆破试验装置满足试验要求，试验灵活方便、控制精度高。
- 包壳管 ,
- 高温爆破 ,
- 爆破强度 ,
- 极限环向应力
Abstract: In order to obtain the high temperature burst properties of the cladding for fuel assembly and core components, high temperature burst facility of thin-walled tube was developed, which is mainly composed of high pressure gas source unit, test atmosphere unit, heating unit, test bench and measurement and control unit. The facility can achieve a maximum test temperature of 1 200 ℃, a maximum heating rate of 10 ℃/s, and a maximum test pressure of 100 MPa. It can complete two kinds of tests: Isothermal high temperature burst under the normal operation condition and transient-heating high temperature burst under the simulated accident condition of PWR. The transient-heating high temperature burst test of 316L stainless steel thin-walled tube was completed by using the facility. The data of high temperature burst strength (ultimate hoop stress) and total circumference elongation were obtained under the conditions of 600-1 200 ℃ and heating rate of 5 ℃/s. The results of verification test of the burst facility and the burst test of the stainless steel thin-walled tube show that the developed high temperature burst facility of thin-walled tube meets the test requirements. And the test is flexible and convenient, with high control accuracy.
- cladding tube ,
- high temperature burst ,
- burst strength ,
- ultimate hoop stress

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参考文献(20)

[1]	EJ 498—89三十万千瓦压水堆核电厂控制棒组件设计和制造技术条件[S]. 北京：中国核工业总公司，1989.
[2]	NB/T 20057.3—2012压水堆核电厂反应堆系统设计堆芯第3部分：燃料组件[S]. 北京：中国原子能出版社，2012.
[3]	NB/T 20057.4—2012压水堆核电厂反应堆系统设计堆芯第4部分：燃料相关组件[S]. 北京：中国原子能出版社，2012.
[4]	NAGASE F, FUKETA T. Behavior of pre-hydrided Zircaloy-4 cladding under simulated LOCA conditions[J]. Nuclear Science and Technology, 2005, 42(2): 209-218.
[5]	KIM J H, LEE M H, CHOI B K, et al. Deformation of Zircaloy-4 cladding during a LOCA transient up to 1 200 ℃[J]. Nuclear Engineering and Design, 2004, 234: 157-164.
[6]	JEONG Y H, PARK S Y, LEE M H, et al. Out-of-pile and in-pile performance of advanced zirconium alloys (HANA) for high burn-up fuel[J]. Nuclear Science and Technology, 2006, 43(9): 977-983.
[7]	NAGASE F, CHUTO T, FUKETA T. Behavior of high burn-up fuel cladding under LOCA conditions[J]. Nuclear Science and Technology, 2009, 46(7): 763-769.
[8]	MCKINNON M A. Cladding strength and pellet relocation testing results from tritium target rods[R]. Richland, Washington: Pacific Northwest Laboratory, 1992.
[9]	张长义，徐远超，杨启法，等. M5合金包壳管高温爆破性能[M]∥中国原子能科学研究院年报. 北京：原子能出版社，2006：220-221.
[10]	周静，王正品，高巍，等. M5合金室温爆破性能研究[J]. 铸造技术，2010，31(4)：433-436.ZHOU Jing, WANG Zhengpin, GAO Wei, et al. Study on the room temperature blasting properties of M5 zirconium alloy[J]. Foundry Technology, 2010, 31(4): 433-436(in Chinese).
[11]	彭继华，李文芳，BECHADE Jean-Luc，等. 织构对锆合金拉伸和爆破性能的影响[J]. 材料研究与应用，2007，1(2)：122-126.PENG Jihua, LI Wenfang, BECHADE Jean-Luc, et al. Study on the effect of texture on tension and burst properties of zirconium alloys[J]. Materials Research and Application, 2007, 1(2): 122-126(in Chinese).
[12]	田春燕，周长善，杨继才，等. Zr-4包壳管高温内压爆破性能研究[C]∥国产Zr-4合金性能研究论文集. 北京：原子能出版社，1994：66-68.
[13]	陈波全，彭倩，洪晓峰，等. 氢化物取向对Zr-4包壳管室温拉伸和爆破性能的影响[J]. 核动力工程，2019，40(1)：60-64.CHEN Boquan, PENG Qian, HONG Xiaofeng, et al. Effect of hydride orientation on tensile and bursting properties of Zr-4 cladding tubes at room temperature[J]. Nuclear Power Engineering, 2019, 40(1): 60-64(in Chinese).
[14]	温敦古，谭军，陈刘涛，等. 核用锆合金包壳管内压爆破试验及性能研究[J]. 材料研究与应用，2016，10(1)：48-52.WEN Dungu, TAN Jun, CHEN Liutao, et al. Study on the burst tests and properties of zirconium alloys for nuclear reactor[J]. Materials Research and Application, 2016, 10(1): 48-52(in Chinese).
[15]	黄玉才，张述诚，尚成宇，等. 压水堆燃料棒锆-4包壳在大破口LOCA条件下的鼓胀爆破实验[J]. 核科学与工程，1997，17(1)：45-51.HUANG Yucai, ZHANG Shucheng, SHANG Chengyu, et al. Zircaloy-4 cladding ballooning and burst experiment on PWR fuel rod under LB-LOCA conditions[J]. Chinese Journal of Nuclear Science and Engineering, 1997, 17(1): 45-51(in Chinese).
[16]	丁学锋，杜彦亭，刘建章，等. 管材内压闭端爆破测试系统的研制[J]. 原子能科学技术，2003，37（增刊）：98-101.DING Xuefeng, DU Yanting, LIU Jianzhang, et al. Development of tester for burst property of close-end tube[J]. Atomic Energy Science and Technology, 2003, 37(Suppl.): 98-101(in Chinese).
[17]	王德华，袁改焕，李恒羽. 核用锆合金管材爆破试验工艺的改进[J]. 稀有金属快报，2006，25(10)：36-38. WANG Dehua, YUAN Gaihuan, LI Hengyu. Improvement of burst test for zirconium alloy tube applied in reactor[J]. Rare Metals Letters, 2006, 25(10): 36-38(in Chinese).
[18]	李江江，杜彦亭，热合曼·艾比布力. 锆管强度检测系统的研究与设计[J]. 液压与气动，2011(9)：25-29.LI Jiangjiang, DU Yanting, Rahman·Hebibul, et al. The study and design of super-high pressure tube burst test system[J]. Chinese Hydraulics & Pneumatics, 2011(9): 25-29(in Chinese).
[19]	ASTM B353-12 (Reapproved 2017)Standard specification for wrought zirconium and zirconium alloy seamless and welded tubes for nuclear service (except nuclear fuel cladding)[S]. USA: ASTM International, 2017.
[20]	ASTM B811-13 (Reapproved 2017)Standard specification for wrought zirconium alloy seamless tubes for nuclear reactor fuel cladding[S]. USA: ASTM International, 2017.