Research on Handling Method of Accelerometer Tripping of Fresh Fuel Assembly Transport Vessel

Jin Yuan; LI Weicai; Chen Jianxin; Zhou Yuemin

doi:10.13832/j.jnpe.2022.02.0096

Volume 43 Issue 2

Apr. 2022

Turn off MathJax

Article Contents

Article Navigation > Nuclear Power Engineering > 2022 > 43(2): 96-101

Jin Yuan, LI Weicai, Chen Jianxin, Zhou Yuemin. Research on Handling Method of Accelerometer Tripping of Fresh Fuel Assembly Transport Vessel[J]. Nuclear Power Engineering, 2022, 43(2): 96-101. doi: 10.13832/j.jnpe.2022.02.0096

Citation:

Jin Yuan, LI Weicai, Chen Jianxin, Zhou Yuemin. Research on Handling Method of Accelerometer Tripping of Fresh Fuel Assembly Transport Vessel[J]. Nuclear Power Engineering, 2022, 43(2): 96-101. doi: 10.13832/j.jnpe.2022.02.0096

Citation:

PDF( 2363 KB)

Research on Handling Method of Accelerometer Tripping of Fresh Fuel Assembly Transport Vessel

doi: 10.13832/j.jnpe.2022.02.0096

China Nuclear Power Technology Research Institute, Shenzhen, Guangdong, 518031, China

Received Date: 2021-01-26
Rev Recd Date: 2021-07-29
Publish Date: 2022-04-02

Abstract

Abstract

Accelerometers mounted on fresh fuel assembly transport vessel are used to monitor the abnormal shock of fuel assemblies during transport. The tripping of the accelerometer indicates that there may be a load that may damage the fuel assembly during transport. In recent years, several tripping events of fresh fuel assembly transport vessel accelerometers happened in domestic nuclear power plants. After the tripping of accelerometer of the transport vessel, it is necessary to evaluate the mechanical integrity and availability of the incident fuel assembly and judge whether it can be used in the reactor. Based on the in-depth analysis of the principle of the accelerometer and the tripping process of the accelerometer, this paper puts forward a general handling method to deal with the tripping of the accelerometer in the transport vessel of the new fuel assembly. The general handling method is used to deal with the tripping event of the new fuel assembly transport vessel accelerometer in a nuclear power plant in recent years, and the result has been adopted by the owner. The general handling method of accelerometer tripping event proposed in this paper can provide an important reference and basis for the subsequent handling of accelerometer tripping event in domestic nuclear power plants.
- Fresh fuel assembly transport vessel,
- Accelerometer,
- Tripping,
- Fuel assemblies

FullText(HTML)

References(21)

References

[1]	生态环境部, 国家市场监督管理总局. 放射性物品安全运输规程: GB 11806—2019[S]. 北京: 中国环境出版社, 2019.
[2]	中华人民共和国国务院. 放射性物品运输安全管理条例: 国务院令第562号[Z]. 北京: 国务院, 2009.
[3]	环境保护部. 放射性物品运输安全监督管理办法: 部令第38号[Z]. 北京: 环境保护部, 2016.
[4]	衣大勇,汪军,郭春秋,等. YJ-1型新燃料组件运输容器的研制[J]. 科技视界,2015(26): 339-341.
[5]	李颖虹,黄灏,周荣生,等. 高温气冷堆新燃料元件运输容器临界安全分析[J]. 核动力工程,2019, 40(6): 64-71.
[6]	许艳涛,马渊睿,李晨,等. 燃料运输容器跌落姿态分析技术[J]. 包装工程,2017, 38(21): 20-24.
[7]	刘广东,吴维亮,朱贺,等. 事故工况下乏燃料运输容器跌落分析[J]. 包装工程,2017, 38(21): 31-34.
[8]	李楠,韩治,汪军,等. 新燃料元件运输容器跌落试验的有限元分析[J]. 核动力工程,2015, 36(5): 18-21.
[9]	郭春秋,邹佳讯,衣大勇,等. 新燃料元件运输容器热工安全分析及试验验证[J]. 原子能科学技术,2016, 50(11): 1992-1997.
[10]	吴春虎,武光明,项嘉玮,等. 新燃料组件运输容器的力学和临界设计研究[J]. 核动力工程,2017, 38(2): 149-155.
[11]	苏艾玲. 放射性物品运输法规在核燃料运输中的实际应用[J]. 物流工程与管理,2018, 40(3): 124-135. doi: 10.3969/j.issn.1674-4993.2018.03.043
[12]	孙树堂,曾亮,李国强,等. 我国PWR燃料组件运输容器定期评价与经验反馈[J]. 包装工程,2018, 39(23): 105-110.
[13]	王勇,曾京,陈盈,等. 核燃料组件铁路运输容器系统在纵向冲击下的安全性分析[J]. 机械科学与技术,2004, 23(4): 487-489+492. doi: 10.3321/j.issn:1003-8728.2004.04.032
[14]	路庆丰,刘洪艳,宫智. 核燃料公路运输模拟中的加速度分析[J]. 物流技术,2017, 36(2): 100-103+159. doi: 10.3969/j.issn.1005-152X.2017.02.024
[15]	何若益,蒲小兵,陈志强,等. CNFC-3G型核燃料容器在运输中的振动数据分析与研究[J]. 物流技术,2015, 34(7): 283-285.
[16]	史晓鹏,张银平,袁本胜. 爆炸荷载作用下应力波衰减规律研究[J]. 矿冶,2010, 19(3): 15-17. doi: 10.3969/j.issn.1005-7854.2010.03.005
[17]	谭捍华,孙进忠,祁生文. 强夯振动衰减规律的研究[J]. 工程勘察,2001(5): 11-14.
[18]	国家能源局. 压水堆核电厂反应堆系统设计堆芯第3部分: 燃料组件: NB/T 20057.3—2012[S]. 北京: 中国原子能出版社, 2012.
[19]	U.S. Nuclear Regulatory Commission. Standard review plan: 4.2 fuel system design review responsibilities[R]. Rockwell: U.S. Nuclear Regulatory Commission, 2007.
[20]	RCC-C. Design and construction rules for fuel assemblies of PWR nuclear power plants: RCC-C 2015[S]. France: AFCEN, 2015.
[21]	焦拥军,肖忠,李云,等. “华龙一号”燃料组件设计研究及验证[J]. 中国核电,2017, 10(4): 478-482+488.