NOMACS-AN IBM-704 CODE FOR DESIGN EVALUATION OF A NUCLEAR POWER PLANT

Technical Report · Tue Aug 20 04:00:00 EDT 1957

OSTI ID:4350137

Scheib, F J

The NOMACS code will analyze the transients of a nuclear power plant on the IBM-704 digital computer. Its basic representation consists of one reactor, two main coolant loops, two steam generators, and one steam system with two turbines. Its unique capabilities for transient analysis include both symmetrical and non-symmetrical loop operation, constant and variable loop flow, natural temperature coefficient and reactor protective system control, manual and automatic initiation of control, and steadystate and transient initial conditions. Its normal driving functions are main turbine throttle position, main coolant flow rate in either or both loops, reactor control rod reactivity, and reactor power. It has provision for automatic calculation of initial conditions, saturated steam-water property tables, varied and unlimited output data, and operation of various portions at different time intervals to minimize machine time. Types of analyses already completed are normal maneuvers, cold water accidents, pumpswitching, and manual scrams using a variety of operating parameters. The current output data include reactor power and reactivity; system temperatures, pressures, and fiow rates; system average temperature; and turbine throttle position. The IBM-704 equipment required includes an 8000-word core and one tape unit. An approximate ratio of machine-to-problem time is 80 to 1. (auth)

• Research Organization: Knolls Atomic Power Lab., Schenectady, N.Y.
• DOE Contract Number: W-31-109-ENG-52
• NSA Number: NSA-12-002407
• OSTI ID: 4350137
• Report Number(s): KAPL-M-SMS-76
• Country of Publication: United States
• Language: English

Related Subjects

COMPUTERS
CONTROL
CONTROL ELEMENTS
COOLANT LOOPS
DIGITAL SYSTEMS
FLUID FLOW
IBM 704
OPERATION
PHYSICS
PLANNING
POWER PLANTS
PRESSURE
PROGRAMMING
REACTIVITY
REACTOR SAFETY
REACTORS
RODS
STEAM
TEMPERATURE
TURBINES