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

Technical Report · Mon Oct 30 23:00:00 EST 1961

OSTI ID:4042759

The capsule A-2 was removed from the WTR reflector hole at the end of the WTR Cycle 13, and was stored in the WTR canal. The in-pile loop has operated for eight months and the test thimble was irradiated a total of 108 days. Tensile tests were completed on the extruded and annealed Zircaloy-4 Phase-II pressure tubes. The tensile properties varied with location in the pressure tube. The lowest values were obtained in the top flange where the material was fully annealed for ten hours at 800 deg C. Increased properties were achieved from working the material during extrusion operations. A shielding ring is provided to prevent streaming through a void generated by the rotating shield volley supports. It was determined that an additional thickness of iron or steel is required to compensate for the loss of shielding from the removal of one foot of concrete at the bottom of the trench. Various portions of the U-tube and fuel assemblies were homogenized in various axial regions for computer studies. The studies indicated a decrease of 500 hours in core life from non-uniform axial burnup. Pressure tube specimens are being tested under the impulsive test burst program. A test specimen experienced a 51% increase in O.D. under 20 impact blows before it failed. Observations of the tested specimens indicated ductilities far in excess of those predicted from the material's behavior in uniaxial tension. Teste on a Zircaloy-stainless steel joint were concluded after an extensive program of testing under various pressure, temperature and bending moment conditions. No sign of leakage was noted throughout the program. Subsequent inspection of the joint showed cracks in the sleeve portion of the joint. Analysis of the test water indicated a chloride content of approx 88 ppm. A test fuel assembly was dismantled and converted to a four baffle design. Modifications were made to the prototype control-rod-drive system. The alignment between ths vertical and horizontal miter gears was improved by charging the mounting of horizontal shaft and bearings. Scram tests were resumed; these tests indicated that the dashpot was acting too soon. The dashpot is being modified. (auth)

• Research Organization: Westinghouse Electric Corp. Atomic Power Dept., Pittsburgh
• NSA Number: NSA-15-023133
• OSTI ID: 4042759
• Report Number(s): WCAP-4055
• Country of Publication: United States
• Language: English

Related Subjects

ANNEALING
BURNUP
COMPUTERS
CONCRETES
CONTROL SYSTEMS
CVTR
DISTRIBUTION
EQUATIONS
EXTRUSION
FABRICATION
FAILURES
HEAVY WATER MODERATOR
HIGH TEMPERATURE
IN PILE LOOPS
INSPECTION
IRRADIATION
JOINTS
LEAKS
LIFETIME
MACHINE PARTS
MATERIALS TESTING
POWER PLANTS
PRESSURE
REACTOR CORE
REACTOR TECHNOLOGY
REACTORS
ROTATION
SHIELDING
SHIELDING MATERIALS
STEELS
TENSILE PROPERTIES
TESTING
TUBES
ZIRCONIUM ALLOYS