APPR-1 REACTOR TRANSIENT ANALYSIS. VOLUME I. BASIC KINETIC MODEL AND EQUATIONS
A basic kinetic model of the primary system coolant loop is developed for the Army Package Power Reactor -1. Externally controlled varlables are control rod insertion and steam generator power output. Equations are derived for solution by analog computer techniques, and include the following considerations: transporting of coolant through primary system piping, core temperature and pressure reactivity coefficients, heat storage capacity of fuel plates, primary and secondary system liquid, and of steam generator tubes, five group delayed neutron contributions, and portion of core power generated outside fuel plates. The significant assumptions made in the derivation include: core considered as a lumped system, with fuel plates at a uniform mean temperature, and with a uniform coolant velocity distribution, steam generator considered as a lumped system, with a uniform shell-side temperature corresponding to saturation, and with a constant over-all heat transfer coefficient, and slug flow in piping, complete mixing in reactor vessel plenum chambers. Refinements in the model, at the expense of increasing the complexity of the mathematical treatment and the associated analog circuitry, are contemplated. (auth)
- Research Organization:
- Alco Products, Inc., Schenectady, N.Y.
- NSA Number:
- NSA-12-010059
- OSTI ID:
- 4326337
- Report Number(s):
- APAE-Memo-127(Vol. I)
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
ANALOG SYSTEMS-- COOLANT LOOPS-- EQUATIONS-- PLANNING-- PRESSURE-- REACTORS-- SM-1-- TRANSIENTS-- WATER COOLANT-- WATER MODERATOR
BOUNDARY CONDITIONS-- COOLANTS-- DISTRIBUTION-- EQUATIONS-- FLUID FLOW-- FUEL ELEMENTS-- HEAT TRANSFER-- MATHEMATICS-- PRESSURE-- REACTORS-- SM-1-- TEMPERATURE-- TRANSIENTS-- VELOCITY-- VESSELS-- WATER COOLANT-- WATER MODERATOR
CONTROL-- CONTROL ELEMENTS-- EQUATIONS-- GENERATORS--
PHYSICS