Published September 1990 | Version v1
Journal article

Subchannel analysis of a critical power test, using simulated BWR 8x8 fuel assembly

  • 1. Nippon Atomic Industry Group Co. Ltd., Kawasaki, Kanagawa (Japan)
  • 2. Toshiba Corp., Kawasaki, Kanagawa (Japan)
  • 3. Toshiba Corp., Yokohama (Japan)
  • 4. Nuclear Power Engineering Test Center, Tokyo (Japan)
  • 5. Tokyo Inst. of Tech. (Japan)
  • 6. Tokyo Univ. (Japan)

Description

Critical power predictions have been compared with the critical power test data obtained in simulated BWR 8x8 fuel rod assemblies. Two analytical methods for the critical power prediction in rod assemblies are used in the prediction, which are the subchannel analysis using the COBRA/BWR subchannel computer code with empirical critical heat flux (CHF) correlations and the liquid film dryout estimation using the CRIPP-3F 'multi-fluid' computer code. Improvements in both the analytical methods were made for spacer effect modeling, though they were specific for application to the current BWR rod assembly type. In general a reasonable agreement was obtained, though comparisons, between the prediction and the obtained test data. (orig.)

Additional details

Publishing Information

Journal Title
Nuclear Engineering and Design
Journal Volume
122
Journal Issue
1-3
Series
Nucl. Eng. Des.
Journal Page Range
235-254
ISSN
0029-5493
CODEN
NEDEA

Conference

Title
3. international topical meeting on nuclear power plant (NPP) thermal hydraulics and operations.
Dates
14-17 Nov 1988.
Place
Seoul (Republic of Korea).