A simplified methodology for the prediction of the small loss-of-coolant accident

Thesis/Dissertation · Fri Jan 01 00:00:00 EST 1988

OSTI ID:5065511

Ward, L W

This thesis describes a complete methodology which has allowed for the development of a faster than real time computer program designed to simulate a small break loss-of-coolant accident in the primary system of a pressurized water reactor. By developing an understanding of the major phenomenon governing the small break LOCA fluid response, the system model representation can be greatly simplified leading to a very fast executing transient system blowdown code. Because of the fast execution times, the CULSETS code, or Columbia University Loss-of-Coolant Accident and System Excursion Transient Simulator code, is ideal for performing parametric studies of Emergency Core Cooling system or assessing the consequences of the many operator actions performed to place the system in a long term cooling mode following a small break LOCA. While the methodology was designed with specific application to the small break loss-of-coolant accident, it can also be used to simulate loss-of-feedwater, steam line breaks, and steam generator tube rupture events. The code is easily adaptable to a personal computer and could also be modified to provide the primary and secondary system responses to supply the required inputs to a simulator for a pressurized water reactor.

• Research Organization: Columbia Univ., New York, NY (USA)
• OSTI ID: 5065511
• Resource Relation: Other Information: Thesis (Ph. D.)
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
LOSS OF COOLANT
COMPUTERIZED SIMULATION
PWR TYPE REACTORS
BLOWDOWN
C CODES
ECCS
FEEDWATER
PARAMETRIC ANALYSIS
PERSONAL COMPUTERS
PIPES
PRIMARY COOLANT CIRCUITS
RUPTURES
STEAM GENERATORS
STEAM SYSTEMS
ACCIDENTS
BOILERS
COMPUTER CODES
COMPUTERS
COOLING SYSTEMS
DIGITAL COMPUTERS
ENERGY SYSTEMS
ENGINEERED SAFETY SYSTEMS
FAILURES
HYDROGEN COMPOUNDS
MICROCOMPUTERS
OXYGEN COMPOUNDS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR PROTECTION SYSTEMS
REACTORS
SIMULATION
VAPOR GENERATORS
WATER
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled