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Title: Local stability tests in Dresden 2 boiling water reactor

This report presents the results of a local stability test performed at Dresden Unit 2 in May 1983 to determine the effect of a new fuel element design on local channel stability. This test was performed because the diameter of the new fuel rods increases the heat transfer coefficient, making the reactor more responsive and, thus, more susceptible to instabilities. After four of the new fuel elements with a 9 x 9 array of fuel rods were loaded into Dresden 2, the test was performed by inserting an adjacent control rod all the way in and then withdrawing it to its original position at maximum speed. At the moment of the test, reactor conditions were 52.7% power and 38.9% flow. Both the new 9 x 9 fuel elements and the standard 8 x 8 ones proved to be locally stable when operating at minimum pump speed at the beginning of cycle in Dresden 2, and no significant difference was found between the behavior of the two fuel types. Finally, Dresden 2 showed a high degree of stability during control rod and normal noise type perturbations.
Authors:
; ; ;
Publication Date:
OSTI Identifier:
5056719
Report Number(s):
ORNL/TM-9054
ON: DE84010612
DOE Contract Number:
AC05-84OR21400
Resource Type:
Technical Report
Resource Relation:
Other Information: Portions are illegible in microfiche products. Original copy available until stock is exhausted
Research Org:
Oak Ridge National Lab., TN (USA)
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; DRESDEN-2 REACTOR; STABILITY; DISTURBANCES; FUEL CHANNELS; FUEL ELEMENTS; PERFORMANCE TESTING; BWR TYPE REACTORS; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTOR CHANNELS; REACTOR COMPONENTS; REACTORS; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS 210100* -- Power Reactors, Nonbreeding, Light-Water Moderated, Boiling Water Cooled