Feedback control systems for non-linear simulation of operational transients in LMFBRs

Technical Report · Wed Aug 01 04:00:00 EDT 1979

DOI:https://doi.org/10.2172/6494842· OSTI ID:6494842

Khatib-Rahbar, M. ^[1]; Agrawal, A. K. ^[1]; Srinivasan, E. S. ^[1]

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1. Brookhaven National Lab. (BNL), Upton, NY (United States). Dept. of Nuclear Energy

Adequate modeling of Plant Control Systems (PCS) for the study of Anticipated Transients Without Scram (ATWS) is of considerable significance in the design, operation and safety evaluation of Liquid-Metal-Cooled Fast Breeder Reactor (LMFBR) systems. To assess the system response to high frequency, low consequence events, the plant needs to be dynamically simulated. The description of analytical and numerical models for PCS that have been developed and incorporated into the loop version of the Super System Code (SSC-L) are described. The importance of detailed modeling of control systems is discussed. Sample transient results obtained for a 10% ramp change of load in 40 s in the Clinch River Breeder Reactor Plant (CRBRP) are also shown.

• Research Organization: Brookhaven National Laboratory (BNL), Upton, NY (United States)
• Sponsoring Organization: USDOE; USNRC
• DOE Contract Number: EY-76-C-02-0016
• OSTI ID: 6494842
• Report Number(s): BNL-NUREG--25497
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220400* -- Nuclear Reactor Technology-- Control Systems
ACCIDENTS
ALKALI METALS
ATWS
BREEDER REACTORS
CLINCH RIVER BREEDER REACTOR
CONTROL ROD DRIVES
CONTROL SYSTEMS
DESIGN
ELEMENTS
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FEEDBACK
FLOW RATE
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MATHEMATICAL MODELS
METALS
OPERATION
POWER REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CONTROL SYSTEMS
REACTOR PROTECTION SYSTEMS
REACTORS
SIMULATION
SODIUM
SODIUM COOLED REACTORS
TRANSIENTS