MODERATOR TRANSIENT TEMPERATURE STUDY
Technical Report
·
OSTI ID:4801620
An IBM 704 computer program is presented to perform a moderator transient temperature study for determination of the fuel element and moderator temperatures as a function of time upon sudden or accelerated reactor power levels. (auth)
- Research Organization:
- General Electric Co. Aircraft Nuclear Propulsion Dept., Cincinnati
- DOE Contract Number:
- AT(11-1)-171
- NSA Number:
- NSA-16-014224
- OSTI ID:
- 4801620
- Report Number(s):
- DC 58-5-51
- Country of Publication:
- United States
- Language:
- English
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