AbstractThe compressible response of a thin film of liquid subjected to a rapid surface pressure pulse and isochoric nuclear heating is investigated in an attempt to determine the spallation behavior. The use of such films to protect the cavity wall of inertial confinement fusion reactors is currently envisioned. The magnitude and temporal dependence of the surface pressure impulse and nuclear heating are estimated based on data from the Prometheus-L, Osirus and Hiball design studies, all of which use the thin film wall protection concept. Compressible hydrodynamic calculations are performed with the CFDLIB code package from LANL. In both the Prometheus and Osirus cases, no spallation is predicted based on the results of these calculations. However, calculated tensile stresses are less than an order of magnitude below theoretical limits, and uncertainties in data and material behavior may push the film response closer to spallation.
急速表面压力脉冲和等容核加热作用下，薄液膜的可压缩响应被研究，以尝试确定其层裂行为。目前设想利用此类液膜来保护惯性约束聚变反应堆的腔壁。基于Prometheus-L、Osirus和Hiball设计研究的数据，估算了表面压力脉冲的幅度和时间依赖性以及核加热效应，这些设计均采用薄液膜壁保护概念。使用来自LANL的CFDLIB代码包进行了可压缩流体动力学计算。在Prometheus和Osirus两种情形下，计算结果表明未预测到层裂。然而，计算得到的拉伸应力低于理论极限不到一个数量级，且数据和材料行为的不确定性可能使液膜响应更接近层裂。