
CONTROLLED SAFETY TEST ROD WITHDRAWAL TRANSIENTS (POWER RANGE). CORE I, SEED 2, EFPH 2248. Section 2. Test Results T-612393-C
Author(s) -
Not Given Author
Publication year - 1961
Language(s) - English
Resource type - Reports
DOI - 10.2172/4045855
Subject(s) - section (typography) , test (biology) , core (optical fiber) , range (aeronautics) , power (physics) , computer science , materials science , geology , physics , telecommunications , composite material , operating system , thermodynamics , paleontology
Tests were conducted to obtain data on the dynamic response of the plant to various power range control rod withdrawal transients. The Reactor plant responded generally as expected. Comparison of data with simulator studies revealed that transients were more severe and had less measurable differences between the 20, 40, and 60% power runs than those transients predicted. (J.R.D.