FIBWR: a steady-state core flow distribution code for boiling water reactors code verification and qualification report. Final report

Technical Report · Wed Jul 01 00:00:00 EDT 1981

OSTI ID:6275512

Ansari, A F; Gay, R R; Gitnick, B J

A steady-state core flow distribution code (FIBWR) is described. The ability of the recommended models to predict various pressure drop components and void distribution is shown by comparison to the experimental data. Application of the FIBWR code to the Vermont Yankee Nuclear Power Station is shown by comparison to the plant measured data.

• Research Organization: Yankee Atomic Electric Co., Framingham, MA (USA)
• OSTI ID: 6275512
• Report Number(s): EPRI-NP-1923; ON: DE81903769; TRN: 81-015955
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
REACTOR CORES
HEAT TRANSFER
HYDRAULICS
COMPUTER CALCULATIONS
MATHEMATICAL MODELS
PRESSURE DROP
VOID FRACTION
ENERGY TRANSFER
FLUID MECHANICS
MECHANICS
REACTOR COMPONENTS
REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100* - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled