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Title: Independent safety evaluation of the CR562 (CR6) control rod test

This report documents the Independent Safety Evaluation performed for the CR562 control rod. CR562 is a reference Series II control rod which has been designated as an experiment (CR-6) since post- irradiation examination has been planned as part of the surveillance program for FFTF control rods. Prior analysis as an experiment has not been required since the test operated within the Technical Specification Limits up to this time. The control rod will be operated beyond the Technical Specification fluence limit during the last 30 days of Cycle 10B. A TDD-1A has been written to support this extension, and this ISE documents the independent review. A similar procedure was used for the CR544 control rod. 9 refs.
Authors:
Publication Date:
OSTI Identifier:
719397
Report Number(s):
WHC-SP--0403
ON: TI89020250
DOE Contract Number:
AC06-87RL10930
Resource Type:
Technical Report
Resource Relation:
Other Information: PBD: Oct 1988
Research Org:
Westinghouse Hanford Co., Richland, WA (United States)
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; CONTROL ELEMENTS; PERFORMANCE TESTING; FFTF REACTOR; REACTOR SAFETY; HEAT TRANSFER; HYDRAULICS; POST-IRRADIATION EXAMINATION; REACTOR ACCIDENTS; REACTOR CORE DISRUPTION; SYSTEM FAILURE ANALYSIS