PATHFINDER ATOMIC POWER PLANT ANALOG SIMULATOR

Technical Report · Wed Jan 31 04:00:00 EST 1962

DOI:https://doi.org/10.2172/4808048· OSTI ID:4808048

Crimmins, D. H.; Mohr, D.; Stone, J. T.

The steady-state and dynamlc characterlstics of the Pathfinder systems were simulated on a dual-console Pace Analog Computer. The derivation of the system equations, the assumptions involved, their numerical evaluation, and their conversion to analog circuitry are described. The Pathfinder system is unique because of the internal nuclear superheater, and controlled, forced recirculation. In simulating this system the following major assumptions were maden the reactor is a boiling-water type; moderated and cooled with saturated, light water; pressurized between 400 and 800 psiai and has a neutron flux distribution that is spatially invariant. All the importanit non-linearities are retained, thus permitting accurate solutions of large system disturbances. The neutron kinetics equations, with their six groups of delayed neutrons, are simulated with power feedbacks through reactor pressure, steam flow, core inlet subcooling, and fuel- element temperature. Particular attention ls devoted to the accurate simulation of fuel-element heat transfer; the reactor pressure-control system, which operates the turbine inlet valves; and the effect of core inlet subcooling, sinee these were found to have pronounced effects on reactor performance. The transient temperatures at the superheater hot spot and exit are generated. Enough flexibility ss included, so that all important disturbanees possible in the actual plant can be run on the slmulator. Changes in system parameters are easily accomplished by merely changing potentiometer settings. The prime objectives of the reactor simulator are to establish a conttrol system for Pathfinder and optimize its settings, to investi-gate system stability under all eonditions, to compute results of postulated system disturbances and accidents, and to help obtasn system characteristics useful in formulating plant operating procedures. (auth)

• Research Organization: Allis-Chalmers Mfg. Co. Atomic Energy Div., Milwaukee
• NSA Number: NSA-16-011183
• OSTI ID: 4808048
• Report Number(s): ACNP-62001
• Country of Publication: United States
• Language: English

Related Subjects

ACCIDENTS
ANALOG SYSTEMS
BOILING
COMPUTERS
CONFIGURATION
CONTROL
CONTROL SYSTEMS
COOLANT LOOPS
DELAYED NEUTRONS
DISTRIBUTION
EQUATIONS
EXCURSIONS
FAILURES
FLUID FLOW
FUEL ELEMENTS
GAS COOLANT
GAS FLOW
HEAT TRANSFER
HIGH TEMPERATURE
NEUTRON FLUX
NUMERICALS
PATHFINDER
POWER PLANTS
PRESSURE
PROGRAMMING
PROMPT NEUTRONS
PUMPS
REACTIVITY
REACTOR CORE
REACTOR TECHNOLOGY
REMOTE CONTROL
STABILITY
STANDARDS
STEAM
SUPERHEATING
TEMPERATURE
TRANSFER FUNCTIONS
TRANSIENTS
TURBINES
VALVES
VARIATIONS
WATER COOLANT
WATER MODERATOR