HOTROD: a computer program for subchannel analysis of coolant flow in rod bundles
Technical Report
·
OSTI ID:4377696
A digital computer program is described for the steady-state thermal and hydraulic subchannel analysis of coolant flow in rod bundle reactor cores and heated-rod experimental test sections. The program allows for the transfer of two-phase fluid properties in three dimensions and predicts the local fluid conditions, fuel rod surface temperature and critical heat flux. The history of subchannel analysis in rod bundles is discussed. A detailed description is presented of the HOTROD analytical model, the numerical solution procedures and the program input formats. (29 references) (auth)
- Research Organization:
- Bettis Atomic Power Lab., Pittsburgh, Pa. (USA)
- NSA Number:
- NSA-29-017559
- OSTI ID:
- 4377696
- Report Number(s):
- WAPD-TM--1070
- Country of Publication:
- United States
- Language:
- English
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