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Title: Prediction of dryout performance for boiling water reactor fuel assemblies based on subchannel analysis with the RINGS code

Abstract

A fuel assembly with a large critical power margin introduces flexibility into reload fuel management. Therefore, optimization of the bundle and spacer geometry to maximize the bundle critical power is an important design objective. With a view to reducing the extent of the complex full-scale tests usually carried out to determine the thermal-hydraulic characteristics of various assembly geometries, the subchannel analysis method was further developed with the Siemens RINGS code. The annular flow code predicts dryout power and dryout location by calculating the conditions at which the liquid film flow rate is reduced to zero, allowing for evaporation, droplet entrainment, and droplet deposition. Appropriate attention is paid to the modeling of spacer effects. Comparison with experimental data of 3 x 3 and 4 x 4 tests shows the capability of RINGS to predict the flow quality and mass flux in subchannels under typical boiling water reactor operating conditions. By using the RINGS code, experimental critical power data for 3 x 3, 4 x 4, 5 x 5, 7 x 7, 8 x 8, 9 x 9, and 10 x 10 fuel assemblies were successfully postcalculated.

Authors:
;  [1]
  1. Siemens AG, Offenbach am Main (Germany). Power Generation Group
Publication Date:
OSTI Identifier:
170252
Resource Type:
Journal Article
Journal Name:
Nuclear Technology
Additional Journal Information:
Journal Volume: 112; Journal Issue: 3; Other Information: PBD: Dec 1995
Country of Publication:
United States
Language:
English
Subject:
21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS; FUEL ASSEMBLIES; SPACERS; DRYOUT; BWR TYPE REACTORS; DESIGN; FUEL CHANNELS; POSITIONING; HEAT TRANSFER; HYDRAULICS; R CODES; CRITICAL HEAT FLUX

Citation Formats

Knabe, P, and Wehle, F. Prediction of dryout performance for boiling water reactor fuel assemblies based on subchannel analysis with the RINGS code. United States: N. p., 1995. Web.
Knabe, P, & Wehle, F. Prediction of dryout performance for boiling water reactor fuel assemblies based on subchannel analysis with the RINGS code. United States.
Knabe, P, and Wehle, F. 1995. "Prediction of dryout performance for boiling water reactor fuel assemblies based on subchannel analysis with the RINGS code". United States.
@article{osti_170252,
title = {Prediction of dryout performance for boiling water reactor fuel assemblies based on subchannel analysis with the RINGS code},
author = {Knabe, P and Wehle, F},
abstractNote = {A fuel assembly with a large critical power margin introduces flexibility into reload fuel management. Therefore, optimization of the bundle and spacer geometry to maximize the bundle critical power is an important design objective. With a view to reducing the extent of the complex full-scale tests usually carried out to determine the thermal-hydraulic characteristics of various assembly geometries, the subchannel analysis method was further developed with the Siemens RINGS code. The annular flow code predicts dryout power and dryout location by calculating the conditions at which the liquid film flow rate is reduced to zero, allowing for evaporation, droplet entrainment, and droplet deposition. Appropriate attention is paid to the modeling of spacer effects. Comparison with experimental data of 3 x 3 and 4 x 4 tests shows the capability of RINGS to predict the flow quality and mass flux in subchannels under typical boiling water reactor operating conditions. By using the RINGS code, experimental critical power data for 3 x 3, 4 x 4, 5 x 5, 7 x 7, 8 x 8, 9 x 9, and 10 x 10 fuel assemblies were successfully postcalculated.},
doi = {},
url = {https://www.osti.gov/biblio/170252}, journal = {Nuclear Technology},
number = 3,
volume = 112,
place = {United States},
year = {Fri Dec 01 00:00:00 EST 1995},
month = {Fri Dec 01 00:00:00 EST 1995}
}