NRC plant-analyzer development at BNL. [BWR]

Conference · Sat Jan 01 00:00:00 EST 1983

OSTI ID:5492588

Wulff, W

The objective of this program is to develop an LWR engineering plant analyzer capable of performing realistic and accurate simulations of plant transients and Small-Break Loss of Coolant Accidents at real-time and faster than real-time computing speeds and at low costs for preparing, executing and evaluating such simulations. The program is directed toward facilitating reactor safety analyses, on-line plant monitoring, on-line accident diagnosis and mitigation and toward improving reactor operator training. The AD10 of Applied Dynamics International, Ann Arbor, MI, a special-purpose peripheral processor for high-speed systems simulation, is programmed through a PDP-11/34 minicomputer and carries out digital simulations with analog hardware in the input/output loop (up to 256 channels). Analog signals from a control panel are being used now to activate or to disable valves and to trip pump drive motors or regulators without interrupting the simulation. An IBM personal computer with multicolor graphics capabilities and a CRT monitor are used to produce on-line labelled diagrams of selected plant parameters as functions of time.

• Research Organization: Brookhaven National Lab., Upton, NY (USA)
• DOE Contract Number: AC02-76CH00016
• OSTI ID: 5492588
• Report Number(s): BNL-NUREG-33665; CONF-8310143-3; ON: DE83014024; TRN: 83-027642
• Resource Relation: Conference: 11. NRC water reactor safety research information meeting, Gaithersburg, MD, USA, 14 Oct 1983; Other Information: Portions are illegible in microfiche products
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
LOSS OF COOLANT
HEAT TRANSFER
HYDRAULICS
REACTOR SIMULATORS
FLOW RATE
PRESSURE GRADIENTS
REACTOR SAFETY
ACCIDENTS
ANALOG SYSTEMS
ENERGY TRANSFER
FLUID MECHANICS
FUNCTIONAL MODELS
MECHANICS
REACTOR ACCIDENTS
REACTORS
SAFETY
SIMULATORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled