The Japanese utilities` expectations for subchannel analysis
Journal Article
·
· Nuclear Technology
OSTI ID:170259
- Tokyo Electric Power Co. (Japan)
Boiling water reactor (BWR) utilities in Japan began to consider the development of a mechanistic model to describe the critical heat transfer conditions in the BWR fuel subchannel. Such a mechanistic model will not only decrease the necessity of tests, but will also help by removing some overly conservative safety margins in thermal hydraulics. With the use of a postdryout heat transfer correlation, new acceptance criteria may be applicable to evaluate the fuel integrity. Mechanistic subchannel analysis models will certainly back up this approach. This model will also be applicable to the analysis of large-size fuel bundles and examination of corrosion behavior.
- OSTI ID:
- 170259
- Journal Information:
- Nuclear Technology, Vol. 112, Issue 3; Other Information: PBD: Dec 1995
- Country of Publication:
- United States
- Language:
- English
Similar Records
Improvement of Predictive Accuracy on Subchannel Analysis Code (NASCA) for Tight-Lattice Rod Bundle Tests - Optimization of UEDA'S Entrainment Model Parameter and Cross Flow Model Parameters
Subchannel Analysis with Mechanistic Methods for Thermo-Hydro Dynamics in BWR Fuel Bundles
Proceedings: Second International Seminar on Subchannel Analysis
Conference
·
Sat Jul 01 00:00:00 EDT 2006
·
OSTI ID:170259
+1 more
Subchannel Analysis with Mechanistic Methods for Thermo-Hydro Dynamics in BWR Fuel Bundles
Conference
·
Sat Jul 01 00:00:00 EDT 2006
·
OSTI ID:170259
+1 more
Proceedings: Second International Seminar on Subchannel Analysis
Technical Report
·
Fri Nov 19 00:00:00 EST 1993
·
OSTI ID:170259