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

Technical Report · Wed Oct 31 04:00:00 EST 1962

OSTI ID:4800667

Impulse burst testing of pressure tube specimens continued using V- notched specimens. Examination of the Phase II U-tube revealed considerable crud deposits. A Zircaloy-stainless steel joint was fabricated with an Inconel sleeve and cycling tests were started. Testing of the control rod system was completed. Several of the components were examined and indicated only nominal wear. The energy absorber, which is intended to absorb the energy of the falling control rod in the event the dashpot is ineffective or the drive line severs, did not function perfectiy; however, the control rod remained in satisfactory condition. Examination of approximately 20% of the fuel rods revealed that approximately 1% of the fuel rods had corroded at the welded ends. (auth)

• Research Organization: Westinghouse Electric Corp. Atomic Power Dept., Pittsburgh
• NSA Number: NSA-16-012758
• OSTI ID: 4800667
• Report Number(s): WCAP-4061
• Country of Publication: United States
• Language: English

Related Subjects

ALUMINUM ALLOYS
CHROMIUM ALLOYS
CONTROL ELEMENTS
COOLANT LOOPS
CORROSION
CRACKS
CVTR
FABRICATION
FAILURES
FUEL ELEMENTS
IMPACT SHOCK
INCONEL ALLOYS
JOINTS
MATERIALS TESTING
MECHANICAL PROPERTIES
MECHANICAL STRUCTURES
MOTORS
NICKEL ALLOYS
NIOBIUM ALLOYS
POWER PLANTS
PRESSURE
REACTOR TECHNOLOGY
RODS
SERVOMECHANISMS
SHUTDOWN
STAINLESS STEELS
TESTING
TITANIUM ALLOYS
TUBES
WEAR
WELDS
ZIRCALOY