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

Technical Report · Tue Oct 30 23:00:00 EST 1962

OSTI ID:4815598

BS>The endurance run on the U-tube was completed in September. The unit cell moderator tank was removed from the test facility and a hydrostatic test was performed on the U-tube. The U-tube was subjected to 2500 psi pressure and held for one and one-half hours. The Conoseal joints at the U-bend, transition joint and refueling port plugs were checked for leakage during this period. No detectable leakage was evidenced at any of the seals. A second Zircaloy- stainless steel joint with an Inconel sleeve was placed on test. Tests with the first joint were successful. A series of additional vacuum drying tests were performed using the Phase II pressure tube with fuel assemblies in both legs. Heat lamps were directed at both legs and the total number of lamps was doubled over the number used for the tests on the Phase I pressure tube. The results indicated a drying time considerably reduced over the time determined by previous tests. The control rod drive system test facility was modified for operation of two control rods simultaneously. Vertical drive shafts simulating the plant drive connection from the mechanism to the miter box were also incorporated. The drive mechanism was modified for operation at two speeds and to receive a larger servomotor. Hot lab work to be performed on fuel rods from CVTR capsules A-2 and A-4 was reviewed in detail with WTR. The ALPS code was modified and debugged in order to investigate accidents in which the pressurizer is allowed to empty. A run was made for the 36-tube, l6 kw per foot core using a single, large size in jection pump. In this case, the pressurizer empties in 9.5 seconds and results in an abrupt reduction in system pressure. Two-phase flow with a large percentage of steam voids occurs at the inlet to the main circulating pumps. The possibility of eliminating this condition by injecting part of the emergency coolant at the inlet side of the main pumps is being investigated. The reduction in system pressure also results in the injection pump operating beyond its flow design point. This problem is being investigated by Stone & Webster. The experimental measurements at the critical facility continued in the 64 cluster half-height core with a 6.5 inch by 6.5 inch micro-pitch with l.l% fuel. The core arrangement was then modifled by changing the micropitch of 16 of the fuel clusters. Measurements were made at two different micro-pitches with this arrangement. Upon completion of this work, the critical experiments were terminated. (auth)

• Research Organization: Westinghouse Electric Corp. Atomic Power Dept., Pittsburgh
• NSA Number: NSA-16-005034
• OSTI ID: 4815598
• Report Number(s): WCAP-4059
• Country of Publication: United States
• Language: English

Related Subjects

ACCIDENTS
ALUMINUM ALLOYS
BOILING
CHROMIUM ALLOYS
CONFIGURATION
CONTROL ELEMENTS
COOLANT LOOPS
CRITICAL ASSEMBLIES
CRITICALITY
CVTR
EXPANSION
FAILURES
FLUID FLOW
FUEL ELEMENTS
GAS FLOW
HEATING
HIGH TEMPERATURE
INCONEL ALLOYS
INJECTION
JOINTS
LABORATORY EQUIPMENT
LEAKS
LOSSES
MACHINE PARTS
MATERIALS TESTING
MEASURED VALUES
MECHANICAL PROPERTIES
MECHANICAL STRUCTURES
MOCKUP
MODERATORS
MOTORS
NEUTRON FLUX
NICKEL ALLOYS
NIOBIUM ALLOYS
POWER PLANTS
PRESSURE
PRESSURE VESSELS
PROGRAMMING
PUMPS
RADIOCHEMISTRY
REACTOR CORE
REACTOR FUELING
REACTOR TECHNOLOGY
REACTORS
RODS
SEALS
SERVOMECHANISMS
SHUTDOWN
STAINLESS STEELS
STEA