FAST REACTOR SAFETY. Progress Report for the Period January 15, 1962
Technical Report
·
OSTI ID:4840613
Theoretical investigations concerning the safety of fast power reactors are described. Development of simplifications and approximations to the equations describing heat transfer in generalized reactor channels are reported. These were tested numerically in predicting the incipience of coolant boiling and fuel melting in a reactor experiencing an exponential power transient. The reactivity studies were concerned with fast reactor operation with a prompt posttive coefficient and a delayed negative reactivity coefficient of the conduction type. Power excursions for step insertions of reactivity and initial powers below the instability threshold were studied by numerical integration of the nonlinear prompt-jumps equations. Over the range tested, as the initial power approaches the instability threshold, the fractional power overshoot in these excursions decreases. (J.R.D.)
- Research Organization:
- United Nuclear Corp. Development Div., White Plains, N.Y.
- NSA Number:
- NSA-16-018672
- OSTI ID:
- 4840613
- Report Number(s):
- UNC-5004
- Country of Publication:
- United States
- Language:
- English
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