Skip to main content
U.S. Department of Energy
Office of Scientific and Technical Information

CAROLINAS VIRGINIA NUCLEAR POWER ASSOCIATES, INC., CVTR PROJECT MONTHLY PROGRESS REPORT, JULY 1961

Technical Report ·
OSTI ID:4838071
A Zircaloy-stainless steel joint was tested under conditions simulating those anticipated in the plant as well as under abnormal conditions. Examination of the joint showed it to still be in good condition. The location of the CVTR source was established between the legs of one of the centrally located pressure tube units. Testing of the control rod system was terminated after 8397 control rod excursions because excessive loads were experienced by the mechanism. The high load was caused by a thrust bearing being pinched between two thrust washers. Examination of bearings and gears did not show any abnormal wear. Coolant void coefficient measurements at the critical facility indicated negative coefficients for core loadings of 1.1% half-height clusters arranged on pitches of 8 x 6.5 in. and 8 x 8 in. Core control evaluations were made to establish the rod requirements for adequate shutdown. A total of 28 rods, 12 of which are boronated, provide adequate shutdown of the first core with 36 fueled U-tubes. Recommendations for the inspection and drying of the pressure tubes during plant life were formulated along with descriptions of the equipment required to perform the tasks. The CVTR in-pile loop was in operation for approximately ten months. Since mid-November 1960, it was irradiated for a total of 150 days. No significant problems were encountered during removal of the experiment from the WTR vessel. (auth)
Research Organization:
Westinghouse Electric Corp. Atomic Power Dept., Pittsburgh
NSA Number:
NSA-15-028820
OSTI ID:
4838071
Report Number(s):
WCAP-4057
Country of Publication:
United States
Language:
English