New flow regime map and heat transfer correlation for tube bundles
The steady generator is a major component is pressurized water reactors. Predicting the response of a steam generator is essential in studying the thermal-hydraulic behavior of a nuclear reactor coolant system. Therefore, many analytical and experimental efforts have been performed to investigate the thermal-hydraulic behavior of steam generators during operational and accident transients. The objective of this study is to accurately predict the behavior of the tube bundle side of steam generators. The RELAPL5/MOD2 computer code consistently underpredicts the degree of superheat. The flow regime transition criteria and heat transfer correlations are modified in an attempt to correctly predict the degree of superheat. This study indicates the need to implement heat transfer correlations and flow regime maps relevant to tube bundle flow situations. RELAP5/MOD2 has been modified to recognize a tube bundle geometry and to chose a flow regime map and heat transfer correlation appropriate for that geometry. A new flow regime map for flow in bundles was developed and implemented in the code.
- Research Organization:
- Texas A M Univ., College Station (USA)
- OSTI ID:
- 5864102
- Report Number(s):
- CONF-881011-
- Journal Information:
- Trans. Am. Nucl. Soc.; (United States), Journal Name: Trans. Am. Nucl. Soc.; (United States) Vol. 57; ISSN TANSA
- Country of Publication:
- United States
- Language:
- English
Similar Records
RELAP5/MOD2 code modifications to obtain better predictions for the once-through steam generator
U-tube steam generator predictions; Bundle convective heat transfer correlations
Related Subjects
210200* -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
42 ENGINEERING
420400 -- Engineering-- Heat Transfer & Fluid Flow
ACCIDENTS
ACCURACY
AIR
BOILERS
BOILING
BUBBLES
COMPUTER CODES
COOLING SYSTEMS
DESIGN
ENERGY SYSTEMS
ENERGY TRANSFER
FLOW MODELS
FLUID FLOW
FLUID MECHANICS
FLUIDS
GASES
GEOMETRY
HEAT TRANSFER
HYDRAULICS
HYDROGEN COMPOUNDS
MATHEMATICAL MODELS
MATHEMATICS
MECHANICS
NUCLEATE BOILING
OPERATION
OPTIMIZATION
OXYGEN COMPOUNDS
PHASE TRANSFORMATIONS
PWR TYPE REACTORS
R CODES
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR OPERATION
REACTORS
SECONDARY COOLANT CIRCUITS
STEAM GENERATORS
TEST FACILITIES
TRANSIENTS
TRANSITION FLOW
TUBES
TURBULENT FLOW
VAPOR GENERATORS
WATER
WATER COOLED REACTORS
WATER MODERATED REACTORS