Analytic solution to verify code predictions of two-phase flow in a boiling water reactor core channel. [CONDOR code]
Abstract
One reliable method that can be used to verify the solution scheme of a computer code is to compare the code prediction to a simplified problem for which an analytic solution can be derived. An analytic solution for the axial pressure drop as a function of the flow was obtained for the simplified problem of homogeneous equilibrium two-phase flow in a vertical, heated channel with a cosine axial heat flux shape. This analytic solution was then used to verify the predictions of the CONDOR computer code, which is used to evaluate the thermal-hydraulic performance of boiling water reactors. The results show excellent agreement between the analytic solution and CONDOR prediction.
- Authors:
- Publication Date:
- Research Org.:
- Westinghouse Electric Corporation Nuclear Fuel Division, Power Systems, P.O. Box 3912 Pittsburgh, Pennsylvania 15230
- OSTI Identifier:
- 5387095
- Resource Type:
- Journal Article
- Journal Name:
- Nucl. Technol.; (United States)
- Additional Journal Information:
- Journal Volume: 62:3
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; 42 ENGINEERING; BWR TYPE REACTORS; REACTOR CORES; COMPUTER CODES; C CODES; PERFORMANCE; TWO-PHASE FLOW; ANALYTICAL SOLUTION; COMPARATIVE EVALUATIONS; ENERGY EFFICIENCY; EVALUATION; FORECASTING; REACTOR CHANNELS; SENSITIVITY ANALYSIS; EFFICIENCY; FLUID FLOW; REACTOR COMPONENTS; REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; 210100* - Power Reactors, Nonbreeding, Light-Water Moderated, Boiling Water Cooled; 420400 - Engineering- Heat Transfer & Fluid Flow
Citation Formats
Chen, K F, and Olson, C A. Analytic solution to verify code predictions of two-phase flow in a boiling water reactor core channel. [CONDOR code]. United States: N. p., 1983.
Web.
Chen, K F, & Olson, C A. Analytic solution to verify code predictions of two-phase flow in a boiling water reactor core channel. [CONDOR code]. United States.
Chen, K F, and Olson, C A. 1983.
"Analytic solution to verify code predictions of two-phase flow in a boiling water reactor core channel. [CONDOR code]". United States.
@article{osti_5387095,
title = {Analytic solution to verify code predictions of two-phase flow in a boiling water reactor core channel. [CONDOR code]},
author = {Chen, K F and Olson, C A},
abstractNote = {One reliable method that can be used to verify the solution scheme of a computer code is to compare the code prediction to a simplified problem for which an analytic solution can be derived. An analytic solution for the axial pressure drop as a function of the flow was obtained for the simplified problem of homogeneous equilibrium two-phase flow in a vertical, heated channel with a cosine axial heat flux shape. This analytic solution was then used to verify the predictions of the CONDOR computer code, which is used to evaluate the thermal-hydraulic performance of boiling water reactors. The results show excellent agreement between the analytic solution and CONDOR prediction.},
doi = {},
url = {https://www.osti.gov/biblio/5387095},
journal = {Nucl. Technol.; (United States)},
number = ,
volume = 62:3,
place = {United States},
year = {Thu Sep 01 00:00:00 EDT 1983},
month = {Thu Sep 01 00:00:00 EDT 1983}
}
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