棒
瞬态(计算机编程)
核工程
轻水反应堆
冷却液
编码(集合论)
热的
材料科学
核燃料
质量保证
压水堆
工程类
机械工程
计算机科学
物理
热力学
运营管理
外部质量评估
医学
替代医学
程序设计语言
集合(抽象数据类型)
病理
操作系统
作者
L.J. Siefken,G.A. Berna,V.N. Shah
标识
DOI:10.1016/0029-5493(85)90169-4
摘要
The FRAP-T6 computer code was developed to model the transient performance of light water reactor fuel rods during reactor transients ranging from mild operational transients to large break loss-of-coolant accidents. The code models all of the thermal, structural, and chemical phenomena needed for the complete evaluation of light water reactor fuel rod performance. The code was developed using rigorous quality assurance procedures and a large assessment data base. The results of assessment show that the code accurately models the response of light water reactor fuel rods.
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