skip to main content

Title: COBRA-IV: the model and the method

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).
Authors:
; ; ; ; ;
Publication Date:
OSTI Identifier:
5358588
Report Number(s):
BNWL-2214
ON: TI86015346
DOE Contract Number:
AC06-76RL01830
Resource Type:
Technical Report
Research Org:
Pacific Northwest Lab., Richland, WA (USA)
Country of Publication:
United States
Language:
English
Subject:
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