scholarly journals Summary report on the HFED (High-Uranium-Loaded Fuel Element Development) miniplate irradiations for the RERTR (Reduced Enrichment Research and Test Reactor) Program

1989 ◽  
Author(s):  
R.L. Senn
Keyword(s):  
Fuel Element ◽  
Summary Report ◽  
Test Reactor

scholarly journals Modeling Loss-of-Flow Accidents and Their Impact on Radiation Heat Transfer

2017 ◽  
Vol 2017 ◽  
pp. 1-15
Author(s):  
Jivan Khatry ◽  
Fatih Aydogan
Keyword(s):  
Heat Transfer ◽  
Fuel Element ◽  
Radiation Heat Transfer ◽  
Nuclear Space ◽  
Radiation Heat ◽  
Uranium Carbide ◽  
Test Reactor ◽  
Fuel Elements ◽  
The Impact

Long-term high payload missions necessitate the need for nuclear space propulsion. The National Aeronautics and Space Administration (NASA) investigated several reactor designs from 1959 to 1973 in order to develop the Nuclear Engine for Rocket Vehicle Application (NERVA). Study of planned/unplanned transients on nuclear thermal rockets is important due to the need for long-term missions. In this work, a system model based on RELAP5 is developed to simulate loss-of-flow accidents on the Pewee I test reactor. This paper investigates the radiation heat transfer between the fuel elements and the structures around it. In addition, the impact on the core fuel element temperature and average core pressure was also investigated. The following expected results were achieved: (i) greater than normal fuel element temperatures, (ii) fuel element temperatures exceeding the uranium carbide melting point, and (iii) average core pressure less than normal. Results show that the radiation heat transfer rate between fuel elements and cold surfaces increases with decreasing flow rate through the reactor system. However, radiation heat transfer decreases when there is a complete LOFA. When there is a complete LOFA, the peripheral coolant channels of the fuel elements handle most of the radiation heat transfer. A safety system needs to be designed to counteract the decay heat resulting from a post-LOFA reactor scram.

scholarly journals AN EVALUATION OF THE SUBSTITUTION OF ZIRCALOY FOR STAINLESS STEEL IN N.S. SAVANNAH FUEL-ELEMENT CONTAINERS. Summary Report

1963 ◽  
Author(s):  
T.D. Anderson ◽  
E.E. Gross ◽  
H.C. McCurdy ◽  
L.D. Schaffer ◽  
L.R. Shobe ◽  
...  
Keyword(s):  
Stainless Steel ◽  
Fuel Element ◽  
Summary Report
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