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TRANSIENT TEMPERATURE ANALYSIS OF THEnFUEL LOADER PUSH ROD AND GUIDE TUBE IN THEnULTRA HIGH TEMPERATURE REACTOR EXPERIMENT (UHTREX)

机译：高温反应堆实验（UHTREX）中燃料负荷推杆和导管的瞬态温度分析

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During the fuel loading procedure in the Ultra High Temperature Reactor Experiment (UHTREX) the fuel loader guide tube is subjected to a high thermal radiation flux. This report examines various means by which the resultant heating of the guide tube may be minimized.

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作者
C. H. Treat;
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年度 1965
页码 1-26
总页数 26
原文格式 PDF
正文语种 eng
中图分类工业技术;
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6. Stress-Rupture of Fiber-Reinforced Ceramic-Matrix Composites with Stochastic Loading at Intermediate Temperatures. Part I: Theoretical Analysis [O] . Longbiao Li 2019

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7. ULTRA HIGH TEMPERATURE REACTOR EXPERIMENT (UHTREX) FACILITY DESCRIPTION AND SAFETY ANALYSIS REPORT. [O] . 1967

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8. Ultra-High Temperature Reactor Experiment (UHTREX) Transients [R] . John C. Vigil 1967

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TRANSIENT TEMPERATURE ANALYSIS OF THEnFUEL LOADER PUSH ROD AND GUIDE TUBE IN THEnULTRA HIGH TEMPERATURE REACTOR EXPERIMENT (UHTREX)

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