CAROLINAS VIRGINIA NUCLEAR POWER ASSOCIATES, INC. QUARTERLY PROGRESS REPORT FOR THE PERIOD JANUARY 1, 1960 TO MARCH 31, 1960

Technical Report · Sun May 01 04:00:00 EDT 1960

OSTI ID:4080749

De Huff, P G

An IBM-704 computer program, HYDNA, is being developed to investigate the transient behavior of the coolant in paarallel channels (pressure tubes) in a closed-channel reactor. Studies were made to determine the effect of reflector thickess on the nuclear and thermal performance of the core. These studies indicated that the reflector thickness could be reduced by 6 in. with only minor effect on the hot-channel factor and fuel burn-up. The Phase I pressure tube- fuel assembly tests were started. The results to date have indicated that the heat losses are higher than anticipated. Two Marman Conoseal fittings were tested in the thermal cycling loop; one a refueling port mock-up and the other a test model of the upper in-pile Zircaloy to 410 stainless-steel transition joint. Both joints performed very well. The jumper tube orifice tests continued. The tests have indicated that a double orifice plate should be tested since it offers promise for reducing erosion. The studies to determine the degree of coolant mixing in the fuel assemblies were continued. The effort is being concentrated on the 12- and 15-in. spacer wire pitches. The test equipment for the measurements of thermal contact resistance between the fuel pellet and clad was designed. After a study of the various control rod drive systems, the decision was made to use a top-mounted gravity-scramming rack-andpinion drive type for CVTR. Efforts to obtain a satisfactory method for permanently affixing spacer wires to the fuel-element cladding were increased. Three methods are being considered: welding or brazing of wire to the cladding or extrusion of cladding with an integral fin. Studies were begun on the preoxidation treatment of Zircaloy. In this process, the Zircaloy is preoxidized in an oxygen atmosphere rather than in steam or water with the purpose of reducing hydrogen pickup. Considerable effort was expended in establishing over-all reactor layouts, incorporating the latest features of the various component designs. A major change, wherein the moderator tank diameter was reduced by 1 ft and the tank suspended from its top, was made. A proposed reduction in primary coolant system design pressure was effected lowering the value from 1800 to 1730 psia. A final conceptual layout of primary coolant system was prepared and integrated into over- all plant design. (For preceding period see CVNA-45.) (auth)

• Research Organization: Westinghouse Electric Corp. Atomic Power Div., Pittsburgh
• NSA Number: NSA-15-012529
• OSTI ID: 4080749
• Report Number(s): CVNA-52
• Country of Publication: Country unknown/Code not available
• Language: English

Related Subjects

BRAZING
CONFIGURATION
CONTROL ELEMENTS
CONTROL SYSTEMS
COOLANTS
CVTR
EXTRUSION
FINNED TUBES
FUEL CANS
FUEL ELEMENTS
MEASURED VALUES
MIXING
PELLETS
PLANNING
REACTOR CORE
REACTOR TECHNOLOGY
REACTORS
RODS
THERMAL CONDUCTIVITY
TRANSPORT
WELDING
WIRES
ZONES