PWR hybrid computer model for assessing the safety implications of control systems
The ORNL study of safety-related aspects of nuclear power plant control systems consists of two interrelated tasks: (1) failure mode and effects analysis (FMEA) that identified single and multiple component failures that might lead to significant plant upsets and (2) computer models that used these failures as initial conditions and traced the dynamic impact on the control system and remainder of the plant. This report describes the simulation of Oconee Unit 1, the first plant analyzed. A first-principles, best-estimate model was developed and implemented on a hybrid computer consisting of AD-4 analog and PDP-10 digital machines. Controls were placed primarily on the analog to use its interactive capability to simulate operator action. 48 refs., 138 figs., 15 tabs.
- Research Organization:
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 5832266
- Report Number(s):
- NUREG/CR-4449; ORNL/TM-9868; ON: TI86008928
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
OCONEE-1 REACTOR
CONTROL SYSTEMS
REACTOR SAFETY
COMPUTERIZED SIMULATION
FAILURE MODE ANALYSIS
MATHEMATICAL MODELS
NEUTRON DIFFUSION EQUATION
NUMERICAL SOLUTION
DIFFERENTIAL EQUATIONS
ENRICHED URANIUM REACTORS
EQUATIONS
POWER REACTORS
PWR TYPE REACTORS
REACTORS
SAFETY
SIMULATION
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled