橡树岭国家实验室
锆合金
核工程
瞬态(计算机编程)
扩散
氧气
裂变产物
材料科学
山脊
子程序
核燃料
核裂变产物
化学
热力学
机械
核物理学
放射化学
冶金
锆
物理
地质学
计算机科学
工程类
古生物学
有机化学
操作系统
作者
F.C. Iglesias,Dugald B. Duncan,S. Sagat,H.E. Sills
标识
DOI:10.1016/0022-3115(85)90292-2
摘要
As the sheath of nuclear fuel elements in a water cooled reactor is one of the principal barriers against the release of fission products into the primary heat transport system, the modelling of the different phenomena that influence the sheath integrity is important. The computer subroutine FROM was developed to model Zircaloy-4 oxidation during an arbitrary high temperature transient. The Zircaloy thickness can contain up to three regions separated by diffusion controlled moving boundaries. Interface oxygen concentrations are not necessarily maintained at equilibrium values. The comparison of FROM predictions of layer thickness with a large number of experimental results from Kermforschungszentrum Karlsruhe (KFK), Oak Ridge (ORNL) and Chalk River (CRNL), showed very good agreement. The model is also successful in prediction of oxygen concentration distributions.
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