微压供热堆HAPPY200总体技术方案
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摘要
以安全、经济、成熟的核能供热技术为目标,研发了微压供热堆HAPPY200。通过对HAPPY200的总体方案设计、系统关键参数、堆芯方案、热工水力设计、结构方案、主要工艺系统方案、设备方案以及安全评价等方面开展论证和分析,完成了整个核供热系统的概念设计。HAPPY200采用基于大容积水池的安全系统,实现了反应堆系统的非能动安全。HAPPY200的技术方案具有高度安全、系统简化、技术成熟、建造周期短、运行维护费用低及供热品质高等特点,具有广阔的市场前景和市场竞争力。目前已完成HAPPY200的概念设计并确定了示范堆的厂址,正在开展工程设计。
Aiming at a safe, economic and mature nuclear heating system, a low-pressurized heating reactor HAPPY200 was developed. The general scheme, key parameters, core scheme, thermal-hydraulic design, structure scheme, main process system scheme, equipment scheme and safety evaluation of the HAPPY200 were designed and analyzed. A safety system based on large volume tank was used by HAPPY200, which provided passive safety for reactor system. The technical scheme of HAPPY200 has the characteristics of high security, simplified system, mature technology, short construction period, low cost of operation and maintenance and high quality of heating. It has a broad market prospect and market competitiveness. At present, the conceptual design of HAPPY200 was completed and the site of demonstration reactor was identified. Engineering design is being carried out.
Aiming at a safe, economic and mature nuclear heating system, a low-pressurized heating reactor HAPPY200 was developed. The general scheme, key parameters, core scheme, thermal-hydraulic design, structure scheme, main process system scheme, equipment scheme and safety evaluation of the HAPPY200 were designed and analyzed. A safety system based on large volume tank was used by HAPPY200, which provided passive safety for reactor system. The technical scheme of HAPPY200 has the characteristics of high security, simplified system, mature technology, short construction period, low cost of operation and maintenance and high quality of heating. It has a broad market prospect and market competitiveness. At present, the conceptual design of HAPPY200 was completed and the site of demonstration reactor was identified. Engineering design is being carried out.
引文
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[4] 郑文祥,董铎.5 MW低温核供热试验堆及其安全特性[J].原子能科学技术,1990,24(6):30-36.ZHEN Wenxiang,DONG Duo.5 MW low temperature nuclear heating test reactor and safety characteristics[J].Atomic Energy Science and Technology,1990,24(6):30-36(in Chinese).
[5] 王大中,董铎,郑文祥.5 MW低温核供热堆的研制和运行特性[J].清华大学学报:自然科学版,1991,31(3):1-11.WANG Dazhong,DONG Duo,ZHEN Wenxiang.Development and operation characteristics of 5 MW low temperature nuclear heating reactor[J].Journal of Tsinghua University:Natural Science Edition,1991,31(3):1-11(in Chinese).
[6] 核电厂安全:设计,IAEA-SSR2-1[R].维也纳:国际原子能机构,2016.
[7] WANG Fangnian,CHEN Yaodong,BAI Ning,et al.Shape characteristics and condensation heat transfer of supersonic steam jet in subcooled water[C]∥Proceedings of the 2017 25th International Conference on Nuclear Engineering.Shanghai:[s.n.],2017.
[8] 白宁,朱元兵,任志豪,等.子通道分析程序LINDEN的开发与初步验证[J].原子能科学技术,2013,47(增刊):299-301.BAI Ning,ZHU Yuanbing,REN Zhihao,et al.Development and verification of sunchannel analysis code LINDEN[J].Atomic Energy Science and Technology,2013,47(Suppl.):299-301(in Chinese).
[9] 白宁,朱元兵,任志豪,等.适用于PWR燃料组件的CHF关系式的开发及评估[J].原子能科学技术,2013,47(增刊):394-397.BAI Ning,ZHU Yuanbing,REN Zhihao,et al.Development and assessment of CHF correlation for PWR fule assembly[J].Atomic Energy Science and Technology,2013,47(Suppl.):394-397(in Chinese).
[10] 孙灿辉,张迪,白宁,等.反应堆低压临界热流关系式评价[C]//北京核学会第十二届(2016年)核应用技术学术交流会文集.北京:北京核学会,2016.
[11] BAI Ning,ZHU Yuanbing,REN Zhihao,et al.The principle and preliminary validation of a new subchannel code[C]//Proceedings of the 2013 21st International Conference on Nuclear Engineering.Chengdu:[s.n.],2013.
[12] BAI Ning,LIU Wei,ZHU Yuanbing,et al.The development and assessment of a new CHF correlation for PWR fuel assemblies[C]//Proceedings of the 2013 21st International Conference on Nuclear Engineering.Chengdu:[s.n.],2013.
[13] SUN Canhui,BAI Ning,ZHANG Di,et al.Analysis of thermal-hydraulic behavior for reduced-height PWR fuel assemblies[C]//NURETH17.[S.l.]:[s.n.],2017.
[14] 朱继洲.压水堆核电站的运行[M].北京:原子能出版社,2000.
[15] Nuclear Safety Analysis Division.RELAP5/MOD3.4 code manual,Volume 1[R].USA:NRC,2001.
[16] XING Mian,BAI Ning,CHEN Yaodong,et al.Preliminary LOCA analysis of heating-reactor of advanced low-pressurized and passive safety system (HAPPY)[C]∥Proceedings of the 2017 25th International Conference on Nuclear Engineering.Shanghai:[s.n.],2017.
[17] XING Mian,CHEN Yaodong,BAI Ning,et al.Preliminary SBO analysis of heating-reactor of advanced low-pressurized and passive safety system (HAPPY)[C]//NURETH17.[S.l.]:[s.n.],2017.