Tritium transport analysis for water cooled ceramic breeder blanket

doi:10.16568/j.0254?6086.201904003

NUCLEAR FUSION AND PLASMA PHYSICS ›› 2019, Vol. 39 ›› Issue (4): 301-308.DOI: 10.16568/j.0254?6086.201904003

• Nuclear Fusion Engineering and Technology • Previous Articles Next Articles

Tritium transport analysis for water cooled ceramic breeder blanket

ZHANG Bing1, 2, ZHAO Xue-li1, 2, MA Xue-bin3, 4, LIU Song-lin1

(1. Institute of Plasma Physics, Chinese Academy of Sciences, Hefei 230031; 2. University of Science and Technology of China, Hefei 230026; 3. Advanced Energy Research Center, Shenzhen University, Shenzhen 518060; 4. College of Optoelectronic Engineering, Shenzhen University, Shenzhen 518060)

Received:2018-08-02 Revised:2019-07-08 Online:2019-12-15 Published:2019-12-16

水冷陶瓷增殖剂包层氚输运分析

张兵1, 2，赵雪丽1, 2，马学斌3, 4，刘松林1

(1. 中国科学院等离子体物理研究所，合肥 230031；2. 中国科学技术大学，合肥 230026； 3. 深圳大学新能源研究中心，深圳 518060；4. 深圳大学光电工程学院，深圳 518060)

作者简介:张兵(1993-)，湖北十堰人，硕士研究生，从事核能与核技术工程研究。
基金资助:
国家重点研发计划(2017YFE0300502)

Abstract

Abstract:

Based on the design of the 2015 version of China Fusion Engineering Test Reactor (CFETR) water cooled ceramic breeder (WCCB) blanket modules surrounding the plasma, a tritium transport model has been developed. Tritium transport analysis has been carried out for each blanket module with different breeding zones, purge gas loop, coolant loop and steam generator. The results indicate that the concentration, permeability and retention of tritium among blanket modules are different. For all of the WCCB blanket modules in CFETR, the tritium retention inside the breeder is 6.62×10^-2g, the tritium retention inside the structural materials is 2.01g, the tritium retention inside purge gas and coolant loop are 4.03×10^-4g and 0.19g respectively, the tritium permeation through the steam generator tube walls is 20mg•y^-1, the tritium permeation from the coolant pipes is 0.1mg•y^-1.

Key words: CFETR, Water cooled ceramic breeder blanket, Tritium analysis

摘要：

基于2015版本中国聚变工程实验堆(CFETR)水冷陶瓷增殖剂(WCCB)包层模块设计特点，建立详细的氚输运分析模型，对不同包层模块(包括不同的增殖区)、载氚气回路、冷却剂回路和蒸汽发生器中的氚输运进行分析。结果表明不同包层模块氚的浓度、渗透量、滞留量均不同，全堆所有包层模块增殖区中氚的滞留量为6.62×10^-2g，结构材料中氚滞留量为2.01g，载氚气和冷却剂回路中氚滞留量分别为4.03×10^-4g和0.19g，氚通过蒸汽发生器的渗透量为20mg×y^-1，冷却剂回路中氚渗透到管道外的量为0.1mg×y^-1。

关键词: 中国聚变工程实验堆, 水冷陶瓷增殖剂包层, 氚分析

CLC Number:

TL64+2

ZHANG Bing1, 2, ZHAO Xue-li1, 2, MA Xue-bin3, 4, LIU Song-lin1. Tritium transport analysis for water cooled ceramic breeder blanket[J]. NUCLEAR FUSION AND PLASMA PHYSICS, 2019, 39(4): 301-308.

张兵1, 2，赵雪丽1, 2，马学斌3, 4，刘松林1. 水冷陶瓷增殖剂包层氚输运分析[J]. 核聚变与等离子体物理, 2019, 39(4): 301-308.

References

[1] Franza F, Boccaccini L V, Ciampichetti A, et al. Tritium transport analysis in HCPB DEMO blanket with the FUS-TPC code[J]. Fusion Eng. Des., 2013, 88(9–10): 2444-2447.
[2] Elisabeta C, Carlos M. Tritium modelling in HCPB breeder blanket at a system level[J]. Fusion Eng. Des., 2017, 124: 687-691.
[3] Pan L, Chen H L, Zeng Q. Tritium transport analysis of HCPB blanket for CFETR[J]. Fusion Eng. Des., 2016, 113: 82-86.
[4] 杨万里. CFETR固态水冷包层氚分析[D]. 合肥: 中国科学技术大学, 2017.
[5] Deng B Q, Li X Z, Huang J H, et al. Computer simulation of tritium inventory and leakage of the fusion experimental reactor of FEB-E[J]. Fusion Science and Technology, 2004, 46(4): 548.
[6] Deng B Q, Li Z X, Feng K M. Tritium well depth, tritium well time and sponge mechanism for reducing tritium retention[J]. Nucl. Fusion, 2011, 51(7): 073041.
[7] Liu S L, Ma X B, Jiang K C, et al. Conceptual design of the water cooled ceramic breeder blanket for CFETR based on pressurized water cooled reactor technology[J]. Fusion Eng. Des., 2017, 124: 865-870.
[8] Chen Y H, Chen L, Liu S L. DEM-CFD study of purge gas flow in pebble bed of WCCB for CFETR (ICONE25-66211)[C]. 25th International Conference on Nuclear Engineering, 2017.
[9] Zhang X K, Liu S L, Li X, et al. Updated neutronics analyses of a water cooled ceramic breeder blanket for the CFETR[J]. Plasma Science and Technology, 2017, 19(11): 92-100.
[10] Jiang K C, Ma X B, Cheng X M, et al. Thermal hydraulic analysis on the whole module of water cooled ceramic breeder blanket for CFETR[J]. Fusion Eng. Des., 2016, 112: 81-88.
[11] Nakamura H, Sakurai S, et al. Case study on tritium inventory in the fusion DEMO plant at JAERI[J]. Fusion Eng. Des., 2006, 81: 1339-1345.
[12] Peeters M M W, Magielsen A J, et al. In-pile tritium release behavior of lithium metatitanate produced by extrusion-spheroidisation-sintering process in EXOTIC -9/1 in the high flux reactor, Petten[J]. Fusion Eng. Des., 2007, 82: 2318-2325.
[13] Cheng X M, Huang K, Liu S L, et al. Thermal hydraulic responses of the primary heat transfer system of the WCCB blanket to accident cases for CFETR[J]. Fusion Eng. Des., 2017, 121: 50-59.
[14] 邓柏权. 聚变堆氚系统设计中的一些重要问题研究(Ⅰ)[J]. 核聚变与等离子体物理, 2013, 33(1): 13-18.

[1]	ZHANG Li-yuan, WANG Xiao-jie , WU Da-jun , TANG Yun-ying , WANG Han-lin, LIU Fu-kun. Preliminary structure design and analysis of CFETR ECRH system launcher [J]. Nuclear Fusion and Plasma Physics, 2024, 44(3): 267-274.
[2]	ZHANG Xi-yang , XU Tie-jun , YAO Da-mao. Design of CFETR divertor cryo-pump pumping system and calculation of effective pumping speed [J]. Nuclear Fusion and Plasma Physics, 2024, 44(3): 275-281.
[3]	JI Hai-biao, XING Yin-long, WU Jie-feng, LIU Zhi-hong , WEN Wei, LIN Xiao-dong. Test and analysis on outgassing performance of insulation material G10 for future fusion reactor [J]. Nuclear Fusion and Plasma Physics, 2024, 44(3): 318-322.
[4]	CHAI Yong-sheng, CUI Li-min, GE Jian, CHEN Zhao-bo, ZHANG Long, PANG Xue-wei. Preliminary design and thermal analysis of CFETR expansion plate cryostat thermal shield [J]. Nuclear Fusion and Plasma Physics, 2024, 44(1): 36-42.
[5]	GAO Ze-shi, , WANG Ya-lei, LI Yan-long, TIAN Wen-xi, CAI Lai-zhong, WU Xue-ke, LIAN Qiang, LI Xin-ze, WANG Zhan-hui. Simulation of CFETR parallel heat flux and blanket power deposition under radial turbulent transport [J]. Nuclear Fusion and Plasma Physics, 2024, 44(1): 65-71.
[6]	HU Bo, HUANG Wen-yu, ZHOU Bing, WANG Xiao-yu, WANG Yan-ling, LU Yong, ZHANG Long, LIU Kuan-cheng. Radioactive leakage analysis in LOCA accident for helium cooling divertor loop of CFETR [J]. Nuclear Fusion and Plasma Physics, 2023, 43(2): 150-155.
[7]	YANG Wen-jun , GONG Xue-yu , GAO Xiang , LI Xiao-e. Preliminary simulation investigation of the energetic particle transport on CFETR [J]. Nuclear Fusion and Plasma Physics, 2023, 43(2): 232-237.
[8]	WANG Jun , WANG Zhan-hui , SHI Yong-fu , LI Jing-chun. 1/2 dimensional integrated simulation of CFETR steady state operation scenario and analysis of the impact of impurity particle ratio [J]. Nuclear Fusion and Plasma Physics, 2023, 43(2): 243-248.
[9]	ZHONG Yun-ke, CHEN Xin, ZHU Gen-liang, YANG En-peng, FU You-kun, CAI Li-jun, LI Qiang . Preliminary RAMI analysis of CFETR 25kW 4.5K helium refrigerator [J]. Nuclear Fusion and Plasma Physics, 2023, 43(1): 55-61.
[10]	YI Wei , HU Chun-dong, , XIE Yuan-lai, , XIE Ya-hong, , LIU Wei , WEI Jiang-long , GU Yu-ming , LIANG Li-zhen, , TAO Ling , CUI Qing-long , ZHAO Yuan-zhe , JIANG Cai-chao , XU Yong-jian, . Design of constant temperature water supply system for CFETR N-NBI verification prototype [J]. Nuclear Fusion and Plasma Physics, 2023, 43(1): 62-67.
[11]	HAO Bao-long , CHEN Wei , LI Guo-qiang , WANG Xiao-jing , WU Bin , GAO Xiang , CFETR TEAM . Application of high energetic particle redistribution model in CFETR [J]. Nuclear Fusion and Plasma Physics, 2023, 43(1): 105-111.
[12]	SONG Qiang, YANG Jin-hong, LU Ye, GUI Teng, WANG Wei-hua. Discharge simulation and electromagnetic simulation analysis of CFETR snowflake divertor configuration [J]. Nuclear Fusion and Plasma Physics, 2022, 42(s1): 144-151.
[13]	XU Wan-yun, WANG Cai-wang, LUO Rong-rong, HUANG Chao, LI Peng-yuan, XU Fa-yong, DENG Hua-lin, CHEN Hui . The conceptual design of maintenance and decommission process for the CFETR tritium-generating blanket and divertor in the hot cell [J]. Nuclear Fusion and Plasma Physics, 2022, 42(4): 378-382.
[14]	HU Chun-dong, LIANG Li-zhen, XIE Yuan-lai, XIE Ya-hong, WEI Jiang-long , GU Yu-ming , JIANG Cai-chao , XU Yong-jian, , ZHAO Yuan-zhe , CHEN Yu-qing. Conceptual design of neutral beam injection system for CFETR [J]. Nuclear Fusion and Plasma Physics, 2022, 42(4): 388-392.
[15]	HOU Bing-lin, LAI Xiao-qiang, XU Wan-yun, WEI Hai-hong . Preliminary concept design of the magnet supports for CFETR [J]. Nuclear Fusion and Plasma Physics, 2022, 42(4): 399-403.

Tritium transport analysis for water cooled ceramic breeder blanket

水冷陶瓷增殖剂包层氚输运分析

PDF

Knowledge

Abstract

Cite this article

share this article

References

Related Articles 15

Recommended Articles

Metrics