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Title: A noninvasive technique for the evaluation of diversion cross flow at the inlet of a simulated fuel rod bundle

Journal Article · · Nucl. Technol.; (United States)
OSTI ID:7013498

Diversion cross flow was characterized from a two-subchannel simulation of a nuclear fuel assembly using a gamma camera. The gamma camera alllowed external monitoring over the length of the test assembly, thereby eliminating experimental problems associated with flow partitioning and an isokinetic withdrawal system, allowing the possibility of noninvasive measurement. The experiment was performed by providing fixed but different flow rates to each subchannel. The higher mass flow rate stream was traced with a gamma-emitting radionuclide, /sup 99m/Tc pertechnetate. Activity in each subchannel was measured by the camera. Diversion length was found to be relatively small and strongly dependent on gap spacing. Effective lateral velocity through the gap was also evaluated. With some exceptions, the results were in good agreement with the predictions of the subchannel analysis computer code COBRA IIIC. At a high inlet axial mass velocity ratio of 4, however, the agreement with the prediction was poor.

Research Organization:
Columbia Univ., Dept. of Applied Physics and Nuclear Engineering, New York, NY (US)
OSTI ID:
7013498
Journal Information:
Nucl. Technol.; (United States), Vol. 80:3
Country of Publication:
United States
Language:
English