Studies of General Corrosion, Stress-Corrosion Cracking and Corrosion-Product Transport in a Supercritical-Water Flow System

超临界水流系统中的一般腐蚀、应力腐蚀开裂和腐蚀产物传输研究

• 批准号: 376374-2008
• 负责人: Cook, William
• 金额: $ 0.21万
• 依托单位: University of New Brunswick
• 依托单位国家: 加拿大
• 项目类别: NSERC/NRCan/AECL Generation IV Energy Technologies Program
• 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=484159
• 关键词: Studies; General; Corrosion; Stress; Cracking

Nuclear power is an attractive energy source in today's society where concern for control of environmental emissions and greenhouse gases is increasing and the expected taxes to be levied on carbon emissions are becoming a reality. The possibility of making our nuclear power plants more efficient and multipurpose to help alleviate these environmental concerns has been gaining much attention and is the focus of the Generation IV International Forum (GIF), an international treaty signed by 13 countries, including Canada, to investigate future nuclear reactor designs. One of the reactor technologies of interest to the GIF is the supercritical water reactor (SCWR). This reactor would use supercritical water (water whose temperature and pressure are above its critical point, 371 degC and 22.1 MPa respectively) to remove the heat from the reactor core and is a logical evolution of current reactor designs. Canada is particularly interested in this design since the pressure-tube configuration of the CANDU reactor is well suited for operation in supercritical conditions. The use of supercritical water to cool the reactor has many benefits including no phase separation (boiling will not occur above the critical point) and higher thermodynamic efficiency of the power cycle due to the much higher temperatures employed (up to 625 degC). For the same net power output as current reactors, the higher efficiencies in a SCWR would result in a smaller reactor that is less costly to build and consumes less fuel thereby reducing used fuel production.

在当今社会中，核电是一种有吸引力的能源，在这种社会中，人们对环境排放和温室气体的控制的关注正在增加，并且对碳排放征收的预期税也正在成为现实。 使我们的核电站更加高效和多功能以帮助减轻这些环境问题的可能性引起了人们的关注，并且是IV代国际论坛（GIF）的重点，这是一项由13个国家（包括加拿大）签署的国际条约，以调查未来的核反应堆设计。 GIF感兴趣的反应堆技术之一是超临界水反应堆（SCWR）。 该反应器将使用超临界水（其温度和压力高于其临界点的水，分别为371度和22.1 MPa）来去除反应堆芯的热量，并且是当前反应器设计的逻辑演化。 加拿大对这种设计特别感兴趣，因为candu反应堆的压力管配置非常适合在超临界条件下运行。 使用超临界水冷却反应器具有许多好处，包括没有相位分离（沸点不会在临界点以上发生），并且由于使用了更高的温度（高达625度），因此功率周期的热力学效率更高。 对于与当前反应堆相同的净功率输出，SCWR中较高的效率将导致较小的反应堆构建成本较小，消耗较少的燃料，从而减少使用的燃料产量。