BWR Refill-Reflood Program, Task 4. 7 - model development: basic models for the BWR version of TRAC

Technical Report · Thu Sep 01 04:00:00 EDT 1983

DOI:https://doi.org/10.2172/5624431· OSTI ID:5624431

Andersen, J G.M.; Chu, K H; Shaug, J C

TRAC (Transient Reactor Analysis Code) is a computer code for best estimate analysis of the thermal hydraulic conditions in a reactor system. The constitutive correlations for shear and heat transfer developed for the Boiling Water Reactor (BWR) version of TRAC are described. A universal flow regime map has been developed to tie the regimes for shear and heat transfer into a consistent package. New models in the areas of interfacial shear, interfacial heat transfer and thermal radiation have been introduced. Improvements have also been made to the constitutive correlations and the numerical methods. All the models have been implemented into the GE version TRACB02 and extensively tested against data.

• Research Organization: General Electric Co., San Jose, CA (USA). Nuclear Fuel and Special Projects Div.
• OSTI ID: 5624431
• Report Number(s): NUREG/CR-2573; EPRI-NP-2375; GEAP-22051; ON: DE84900087
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BWR TYPE REACTORS
COMPUTER CALCULATIONS
DATA
ENERGY TRANSFER
EXPERIMENTAL DATA
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
INFORMATION
LOSS OF COOLANT
MECHANICS
NUMERICAL DATA
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
SAFETY
TEMPERATURE GRADIENTS
THEORETICAL DATA
VOID FRACTION
WATER COOLED REACTORS
WATER MODERATED REACTORS