Thermal hydraulic analysis of fuel rod cluster for 100 MWt
Technical Report
·
OSTI ID:4307206
From symposium on nuclear science and engineering; Bombay, India (13 Mar 1973). Computer programs HECTIC and COBRA are used to evaluate the sub-channel coolant temperatures and surface temperatures in fuel rod clusters of various dimensions and configurations. The analysis was carried out for different values of the various parameters such as coolant velocity, eddy diffusivity adjusting factor etc. The results of the analysis and the conclusions derived are discussed. The programs are used to carry out the thermal hydraulic analysis of the 7 rod fuel bundle proposed for the 100 MW(t) research reactor. (auth)
- Research Organization:
- Bhabha Atomic Research Centre, Bombay (India)
- NSA Number:
- NSA-29-031256
- OSTI ID:
- 4307206
- Report Number(s):
- INIS-mf--1161
- Country of Publication:
- India
- Language:
- English
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