Experiments on heat transfer in rod-bundle flows as supercritical pressures

超临界压力下棒束流传热实验

• 批准号: 421838-2011
• 负责人: Tavoularis, Stavros
• 金额: $ 5.83万
• 依托单位: University of Ottawa
• 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: 2013
• 资助国家: 加拿大
• 起止时间: 2013-01-01 至 2014-12-31
• 项目状态: 已结题
• 来源: https://www.nserc-crsng.gc.ca/ase-oro/Details-Detailles_eng.asp?id=531767
• 关键词: Experiments; heat; transfer; rod; bundle

The proposed research is in support of the Canadian National Program on Generation IV Energy Technologies for the development of a Super Critical Water-cooled Reactor (SCWR), which, compared to existing nuclear reactors, is expected to have increased safety, lower-cost electricity production, more compact size and reduced volume of nuclear wastes. The main objective of this research is to quantify the following three important effects on the heat transfer in flows in a three-rod bundle under near-critical and supercritical pressures: i) effect of flow direction, namely downflow vs. upflow; ii) effect of wire wrap spacers; and iii) effect of transients in pressure, mass flux and heat flux. These effects have not been investigated previously for conditions relevant to SCWRs; they need to be quantified in order to improve the SCWRs safety analysis codes and thus make their prediction of thermal behaviour of the SCWR fuel during normal and accidental conditions more realistic. All experimental investigations will be performed in the University of Ottawa's supercritical loop with carbon dioxide as a surrogate fluid.

拟议的研究是为了支持加拿大国民针对IV代能源技术的计划，以开发超关键的水冷反应堆（SCWR），该反应堆（SCWR）与现有的核反应堆相比有望提高安全性，低成本电力生产，更紧凑的大小和核废物的体积减少。这项研究的主要目的是量化以下三种重要的影响在近乎临界和超临界压力下的三杆束中的热传递的三个重要影响：i）流动方向的影响，即下降与上流； ii）电线垫片的效果； iii）压力，质量通量和热通量的瞬变影响。这些效果先前尚未针对与SCWR相关的条件进行调查。为了改善SCWR分析代码，需要对其进行量化，从而使它们在正常和意外条件下对SCWR燃料的热行为的预测更加现实。所有实验研究都将在渥太华大学的超临界循环中进行，二氧化碳作为替代流体。