Optimization of Carbonization Process in Manufacture of Fuel Elements for HTGR

LU Zhen-ming; ZHANG Jie; ZHOU Xiang-wen; LIU Bing; TANG Ya-ping

Volume 34 Issue 5

Mar. 2025

Turn off MathJax

Article Contents

Abstract

References

Article Navigation > Nuclear Power Engineering > 2013 > 34(5): 71-75

LU Zhen-ming, ZHANG Jie, ZHOU Xiang-wen, LIU Bing, TANG Ya-ping. Optimization of Carbonization Process in Manufacture of Fuel Elements for HTGR[J]. Nuclear Power Engineering, 2013, 34(5): 71-75.

Citation:

LU Zhen-ming, ZHANG Jie, ZHOU Xiang-wen, LIU Bing, TANG Ya-ping. Optimization of Carbonization Process in Manufacture of Fuel Elements for HTGR[J]. Nuclear Power Engineering, 2013, 34(5): 71-75.

LU Zhen-ming, ZHANG Jie, ZHOU Xiang-wen, LIU Bing, TANG Ya-ping. Optimization of Carbonization Process in Manufacture of Fuel Elements for HTGR[J]. Nuclear Power Engineering, 2013, 34(5): 71-75.

Citation:

LU Zhen-ming, ZHANG Jie, ZHOU Xiang-wen, LIU Bing, TANG Ya-ping. Optimization of Carbonization Process in Manufacture of Fuel Elements for HTGR[J]. Nuclear Power Engineering, 2013, 34(5): 71-75.

PDF( 1640 KB)

Optimization of Carbonization Process in Manufacture of Fuel Elements for HTGR

Key Lab of Advanced Reactor Engineering and Safety of Ministry of Education, Institution of Nuclear and New Energy Technology, Tsinghua University, Beijing, 100084, China

Received Date: 2012-07-05
Rev Recd Date: 2012-12-10

Available Online: 2025-03-08

Abstract

Abstract

The decomposition process of phenolic resin which is a binder of spherical fuel elements matrix material for high temperature gas-cooled reactor（HTGR） was studied by means of TG-IR and DSC at the temperature of 20～800 ℃.The thermal expansion characteristics of graphite ball samples were investigated through thermal mechanical analysis（TMA）.The results showed that the phase transition of the phenolic resin occurred at the temperature of 50～70℃ and the decomposition had two continuous exothermic stages.Accordingly,the graphite ball samples were expanded and shrink successively during carbonization.The properties of the matrix material made through four-stages heating process completely satisfied the design requirements and the production efficiency of carbonization was increased by 71%.Studies showed that the heating process established according to the sample’s size varied with carbonization temperature under dynamic conditions is more reasonable and the volume change caused by condensation is the critical factor to heating rate.
- HTGR,
- Spherical fuel element,
- Carbonization,
- Phenolic resin

FullText(HTML)

References(0)

References

Relative Articles

[1]	Zhu Tenghao, Wang Hongtao, Wang Haitao. Research on Vibration-induced Noise Simulation of Main Control Room of High-temperature Gas-cooled Reactor[J]. Nuclear Power Engineering, 2024, 45(6): 132-138. doi: 10.13832/j.jnpe.2024.06.0132
[2]	Ni Man, Zhao Jun, Qian Hongtao, Zhang Jiajia, Gong Yu, Xiao Jun. Study on Risk-informed SSC Safety Classification of High Temperature Gas-cooled Reactor[J]. Nuclear Power Engineering, 2024, 45(3): 193-198. doi: 10.13832/j.jnpe.2024.03.0193
[3]	Liu Malin, Cheng Xinyu, Liu Bing, Wang Taowei, Liu Zebing, Yang Xu, Liu Rongzheng, Shao Youlin. Preparation and Performance Evaluation of Fuel Elements for Ultra-high Temperature Gas-cooled Reactors[J]. Nuclear Power Engineering, 2024, 45(S2): 231-237. doi: 10.13832/j.jnpe.2024.S2.0231
[4]	Lin Xiaoling, Liu Cuihong. Diagnostic Method for Damage Equivalent of Reactor Fuel Elements[J]. Nuclear Power Engineering, 2022, 43(5): 115-118. doi: 10.13832/j.jnpe.2022.05.0115
[5]	Huang Yongzhong, Li Quan, Li Yuanming, Pang Hua, Lu Huaiyu, Liu Zhenhai, Qi Feipeng. Research on Analysis Method for Performance of Fuel Element Based on Thermal-Fluid-Solid Coupling[J]. Nuclear Power Engineering, 2021, 42(4): 112-118. doi: 10.13832/j.jnpe.2021.04.0112
[6]	Huang Yongzhong, Li Yuanming, Li Wenjie, Li Quan, Chai Xiaoming, Zhao Bo, Tang Changbing. Design and Optimization of Typical Cells of Solid Core for Heat Pipe Reactor[J]. Nuclear Power Engineering, 2021, 42(6): 87-92. doi: 10.13832/j.jnpe.2021.06.0087
[7]	Jiang Zhuoer, Zhao Jun, WangHaitao, Shi Li, Wang Xiaoxin, Sun Weidong. Fragility Research for Storage Batteries of High Temperature Gas-Cooled Reactor[J]. Nuclear Power Engineering, 2020, 41(4): 105-110.
[8]	Li Yinghong, Huang Hao, Zhou Rongsheng, Yang Xiaodong. Criticality Safety Calculation and Analysis of Fresh Fuel Element Transport Containers for High Temperature Gas-Cooled Reactor[J]. Nuclear Power Engineering, 2019, 40(6): 64-71. doi: 10.13832/j.jnpe.2019.06.0064
[9]	Zhang Ruixiang, Zhao Feng, Peng Weichao, Yao Yao, Wang Zhen, Xu Haosong. Research on Controlling Method of Secondary Circuit Water Quality of High Temperature Gas Cooled Reactor[J]. Nuclear Power Engineering, 2018, 39(5): 106-110. doi: 10.13832/j.jnpe.2018.05.0106
[10]	Wang Huacai, Tang Qi, Fu Cheng, Liang Zhengqiang. Raman Spectroscopy Analysis of Oxide Film Formed on Cladding of Spent Fuel Rod from Nuclear Power Plants[J]. Nuclear Power Engineering, 2017, 38(S1): 110-114. doi: 10.13832/j.jnpe.2017.S1.0110
[11]	Liu Yang, Wang Jun. Heat Transfer Simulation of Fuel Transport Cask for High Temperature Gas Cooled Reactor[J]. Nuclear Power Engineering, 2017, 38(5): 160-163. doi: 10.13832/j.jnpe.2017.05.0160
[12]	Bo Wen, Li Zhengcao, Wang Haitao, Shi Li. Research on Shape Optimization of RPV Opening of High Temperature Gas-Cooled Reactor Using Boundary Element Method[J]. Nuclear Power Engineering, 2016, 37(4): 24-27. doi: 10.13832/j.jnpe.2016.04.0024
[13]	Wang Yongfu, Sun Yuliang. Technical-Economic Study on High Temperature Reactor for Combined Heat and Power Generation[J]. Nuclear Power Engineering, 2016, 37(3): 181-184. doi: 10.13832/j.jnpe.2016.03.0181
[14]	Kuang Liuwei, Jiang Linzhi, Ren Liang, Yu Feiyang, Guo Chengming. Measurement Technology for Fission Gas of Irradiated HWR Fuel Elements[J]. Nuclear Power Engineering, 2016, 37(6): 86-89. doi: 10.13832/j.jnpe.2016.06.0086
[15]	Liu Dan, Sun Jun, Sun Yuliang. Dynamic Model and Analyses of Supercritical Steam Generator of High Temperature Gas-Cooled Reactor[J]. Nuclear Power Engineering, 2015, 36(2): 122-126. doi: 10.13832/j.jnpe.2015.02.0122
[16]	Xie Bo, Ceng Yong, Zhang Hongxiang. Development of Detection System for Fuel Element Cladding Damage Based on ¹³⁷Cs and ⁸⁵Kr Nuclides[J]. Nuclear Power Engineering, 2015, 36(2): 55-57. doi: 10.13832/j.jnpe.2015.02.0055
[17]	LI Yuanming, XIE Qingqing, XIN Yong, ZHOU Yi. Cladding Surface Temperature Limit for Fuel Element Aluminum-Alloy Cladding of Research and Test Reactors[J]. Nuclear Power Engineering, 2015, 36(6): 154-157. doi: 10.13832/j.jnpe.2015.06.0154
[18]	Luo Chending, Zhao Fuqiang, Zhou Jie, Zhang Na. Thermodynamic Analysis of High Temperature Gas-cooled Reactor He/Ammonia Combined Cycle[J]. Nuclear Power Engineering, 2014, 35(1): 165-169.
[19]	ZHOU Xiangwen, HAO Shaochang, ZHAO Xingyu, MA Jingtao, WANG Yang, DENG Zhangsheng. Wet Process of External Gelation of Uranium for Preparation of Uranium Dioxide Kernel of High Temperature Gas-cooled Reactors[J]. Nuclear Power Engineering, 2012, 33(4): 40-43.
[20]	WANG Hai-tao, WU Xin-xin. Research on Creep and Fatigue Characteristics of MSIV at Elevated Temperature in HTR[J]. Nuclear Power Engineering, 2011, 32(S1): 18-21.