| タイトル | Program ELM: A tool for rapid thermal-hydraulic analysis of solid-core nuclear rocket fuel elements |
| 本文（外部サイト） | http://hdl.handle.net/2060/19930009917 |
| 著者（英） | Walton, James T. |
| 著者所属（英） | NASA Lewis Research Center |
| 発行日 | 1992-11-01 |
| 言語 | eng |
| 内容記述 | 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. |
| NASA分類 | SPACECRAFT PROPULSION AND POWER |
| レポートNO | 93N19106
NASA-TM-105867
E-7330
NAS 1.15:105867 |
| 権利 | No Copyright |
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