Three-dimensional numerical simulation for two-phase flow systems. [PWR; BWR]

Conference · Sun Jan 01 00:00:00 EST 1978 · Trans. Am. Nucl. Soc.; (United States)

OSTI ID:6385224

Lee, W H; Shah, V L; Sha, W T

• Research Organization: Argonne National Lab., IL
• OSTI ID: 6385224
• Report Number(s): CONF-7811109-; TRN: 79-005271
• Journal Information: Trans. Am. Nucl. Soc.; (United States), Vol. 30; Conference: 1978 winter meeting of American Nuclear Society, Washington, DC, USA, 12 Nov 1978
• 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
PWR TYPE REACTORS
COMPUTER CODES
REACTOR SAFETY
TWO-PHASE FLOW
ACCIDENTS
ENERGY TRANSFER
FLUID FLOW
FLUID MECHANICS
MECHANICS
REACTOR ACCIDENTS
REACTORS
SAFETY
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled