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Title: Program ELM: A tool for rapid thermal-hydraulic analysis of solid-core nuclear rocket fuel elements

Technical Report ·
OSTI ID:6922303

This report reviews the state of the art of thermal-hydraulic analysis codes and presents a new code, Program ELM, for analysis of fuel elements. ELM is a concise computational tool for modeling the steady-state thermal-hydraulics of propellant flow through fuel element coolant channels in a nuclear thermal rocket reactor with axial coolant passages. The program was developed as a tool to swiftly evaluate various heat transfer coefficient and friction factor correlations generated for turbulent pipe flow with heat addition which have been used in previous programs. Thus, a consistent comparison of these correlations was performed, as well as a comparison with data from the NRX reactor experiments from the Nuclear Engine for Rocket Vehicle Applications (NERVA) project. This report describes the ELM Program algorithm, input/output, and validation efforts and provides a listing of the code.

Research Organization:
National Aeronautics and Space Administration, Cleveland, OH (United States). Lewis Research Center
OSTI ID:
6922303
Report Number(s):
N-93-19106; NASA-TM-105867; E-7330; NAS-1.15:105867; CNN: RTOP 593-71-00
Country of Publication:
United States
Language:
English

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