Validation & Verification for Critical Heat Flux and CFD

必须彻底分析核反应堆在一系列正常运行和(特别是)故障情况下的行为。模拟流体流动的计算机程序(如“计算流体动力学代码，或CFD代码”)原则上可以对此有所帮助。然而，要分析的现象非常复杂，这些代码需要根据在合适的实验台上进行的良好测量进行彻底验证。根据这项提议，一组英国研究人员将与印度BARC的同事合作，那里有很好的这样的实验设施。实验将联合设计和分析，并用于验证这些代码。

The behaviour of nuclear reactors must be thoroughly analysed under a range of normal operation and (especially) fault conditions. Computer programmes that simulate the flow of fluids, (such as 'Computational Fluid Dynamics codes, or CFD codes') can in principle help with this. However, the complexities of the phenomena to be analysed are such that these codes need to be thoroughly validated against good measurements made in suitable experimental rigs. Under this proposal a team of UK researchers will collaborate with colleagues at BARC in India, where there are excellent such experimental facilities available. Experiments will be designed and analysed jointly, and used to validate such codes.