Potential for interactive/real time nuclear power plant simulation with RELAP5

Technical Report · Thu Jan 01 00:00:00 EST 1981

OSTI ID:6225181

Wagner, R J; Ransom, V H; Ybarrondo, L J

RELAP5 is a computer code, used to simulate transients in light water reactors and was designed primarily for large and small break loss-of-coolant and operational transients. Development emphasized fast running, ease of use, and sufficient accuracy for most calculations. Models used in RELAP5 are briefly described and applications of the code to Semiscale and LOFT experiments are illustrated. Planned research at INEL to use RELAP5 in interactive, real time, and ultimately predictive modes are discussed.

• Research Organization: EG and G Idaho, Inc., Idaho Falls (USA)
• DOE Contract Number: AC07-76ID01570
• OSTI ID: 6225181
• Report Number(s): CONF-810113-3; ON: DE85004752
• Resource Relation: Conference: Simulation methods for nuclear power systems conference, Tucson, AZ, USA, 1 Jan 1981; Other Information: Paper copy only, copy does not permit microfiche production
• 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
HEAT TRANSFER
HYDRAULICS
PWR TYPE REACTORS
COMPUTER CODES
EXPERIMENTAL DATA
FLOW RATE
GRAPHS
NUCLEAR POWER PLANTS
PRESSURE GRADIENTS
REACTOR SAFETY
TEMPERATURE GRADIENTS
THEORETICAL DATA
TRANSIENTS
ACCIDENTS
DATA
ENERGY TRANSFER
FLUID MECHANICS
INFORMATION
MECHANICS
NUCLEAR FACILITIES
NUMERICAL DATA
POWER PLANTS
REACTOR ACCIDENTS
REACTORS
SAFETY
SIMULATION
THERMAL POWER PLANTS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled