Heat transfer at supercritical pressures

超临界压力下的传热

• 批准号: 342827-2007
• 负责人: Pioro, Igor
• 金额: $ 1.53万
• 依托单位: University of Ontario Institute of Technology
• 依托单位国家: 加拿大
• 项目类别: Discovery Grants Program - Individual
• 财政年份: 2011
• 资助国家: 加拿大
• 起止时间: 2011-01-01 至 2012-12-31
• 项目状态: 已结题
• 来源: https://www.nserc-crsng.gc.ca/ase-oro/Details-Detailles_eng.asp?id=482512
• 关键词: Heat; transfer; supercritical; pressures

Water-cooled nuclear reactors operating at subcritical pressures (10 - 16 MPa) started to be developed at the end of 1940s and have been used for the last fifty years. At the same time, i.e., as early as the 1950s, concepts of SuperCritical Water-cooled nuclear Reactors (SCWRs) were studied in the USA and Russia. Currently, several countries (Canada, European Union, Japan, Korea, Russia, and USA) have started to work in that direction, building on the successful international deployment of supercritical and ultra-supercritical boilers and turbines for coal-fired power plants. The main objectives of using supercritical water in nuclear reactors are:

在亚临界压力(10-16兆帕)下运行的水冷核反应堆于20世纪40年代末开始开发，在过去的50年里一直在使用。与此同时，早在20世纪50年代，美国和俄罗斯就开始研究超临界水冷核反应堆的概念。目前，几个国家(加拿大、欧盟、日本、韩国、俄罗斯和美国)已经开始朝这个方向努力，在成功地在国际上部署用于燃煤电厂的超临界和超超临界锅炉和涡轮机的基础上。在核反应堆中使用超临界水的主要目标是：