COBRA-IV: the model and the method

Technical Report · Fri Jul 01 00:00:00 EDT 1977

DOI:https://doi.org/10.2172/5358588· OSTI ID:5358588

Stewart, C W; Wheeler, C L; Cena, R J; McMonagle, C A; Cuta, J M; Trent, D S

The objective of this report is to present the mathematical basis of the COBRA-IV computer program (Wheeler et al., 1976) being developed by Battelle, Pacific Northwest Laboratory. The COBRA-IV code is an extended version of the COBRA-IIIC subchannel analysis code that computes the flow and enthalpy distributions in nuclear fuel rod bundles and cores for both steady state and transient conditions (Rowe, 1973).

• Research Organization: Pacific Northwest National Lab. (PNNL), Richland, WA (United States)
• DOE Contract Number: AC06-76RL01830
• OSTI ID: 5358588
• Report Number(s): BNWL-2214; ON: TI86015346
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
42 ENGINEERING
HEAT TRANSFER
C CODES
HYDRAULICS
NUCLEAR POWER PLANTS
ROD BUNDLES
FUEL RODS
MATHEMATICAL MODELS
STEADY-STATE CONDITIONS
TRANSIENTS
COMPUTER CODES
ENERGY TRANSFER
FLUID MECHANICS
FUEL ELEMENTS
MECHANICS
NUCLEAR FACILITIES
POWER PLANTS
REACTOR COMPONENTS
THERMAL POWER PLANTS
220200* - Nuclear Reactor Technology- Components & Accessories
420400 - Engineering- Heat Transfer & Fluid Flow