| 超临界水冷堆述评 |
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| 引用本文： | 陆道纲,彭常宏.超临界水冷堆述评[J].原子能科学技术,2009,43(8):743-749. |
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| 作者姓名： | 陆道纲 彭常宏 |
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| 作者单位： | 1.华北电力大学 ;核科学与工程学院，北京 ;102206；2.中科华核电技术研究院 ;概率安全与可靠性研究所，广东 ;深圳 ;518026 |
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| 摘 要： | 超临界水冷堆(SCWR)是在高于水的临界点（374℃，22.1MPa）的温度和压力下运行的反应堆。相对于传统的轻水堆，它的热效率显著提高，可达45％。由于冷却剂在超临界状态下不发生相变，可直接与能量转换设备相联，从而简化了反应堆的结构。在SCWR中不需再循环和射流泵、稳压器、蒸汽发生器、汽水分离器和干燥器。它的主要特点是经济性好。
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| 关 键 词： | 超临界水冷堆 概念设计 安全性 |
| 收稿时间： | 2008-05-23 |
| 修稿时间： | 2008-07-25 |
Review of Supercritical Water Cooled Reactor |
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| LU Dao-gang,PENG Chang-hong.Review of Supercritical Water Cooled Reactor[J].Atomic Energy Science and Technology,2009,43(8):743-749. |
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| Authors: | LU Dao-gang PENG Chang-hong |
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| Affiliation: | 1.School of Nuclear Science and Engineering, North China Electric Power University, Beijing 102206, China; 2.Probabilistic Safety Assessment and Reliability Analysis Branch, China Nuclear Power Technology Research Institute, Shenzhen 518026, China |
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| Abstract: | The supercritical water cooled reactor (SCWR) is essentially light water reactor (LWR) operating at higher pressure and temperature beyond the thermodynamic critical point of water (374 ℃, 22.1 MPa). Compared to current generation LWR, the efficiency of a SCWR can approach 45%. With operation beyord the critical pressure the coolant remains single-phase throughout the system. Thus, recirculation and jet pumps, pressurizer, steam generators, and steam separators and dryers in current LWR are all eliminated. The main mission of the SCWR is generation of low-cost electricity. |
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| Keywords: | supercritical water cooled reactor conceptual design safety characteristic |
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