CAROLINAS VIRGINIA NUCLEAR POWER ASSOCIATES, INC. CVTR PROJECT MONTHLY PROGRESS REPORT, OCTOBER 1959

Technical Report · Tue Oct 31 04:00:00 EST 1961

OSTI ID:4076403

A preliminary equipment specification for the design, development, and test of an upward scramming controlrod drive mechanism was prepared. An order was placed for the fabrication of CVTR critical exoeriment fuel elements. Task 5.00, irradiation experiments, was revised to include additional exposure irradiation tests on tensile, impact, and creep sample specimens of Zircaloy. Corrosion tests were initiated on samples of several possible CVTR control-rod materials and also on various samples of Zircaloy-2 brazed specimens. Construction was stanted on a thermal cycling facility to test gasketed fittings. An order was placed for the manufacture of seal welding and cutting equipment. This equipment will be used to test the feasibility of repeated welding and cutting of prototype seal weld designs. A study of the AECL work on magnesia- insulated thermal baffles was initiated. Design and layout work were initiated toward applying such a concept to CVTR. Partial analysis of the data obtained from Loop E tests on the fuel assembly showed that the spacer wire pitch has a significant effect on the pressure drop. A study was completed on the design of a gas sweep system that will eliminate the need for seals between the U-tubes and the top neutron shield. (auth)

• Research Organization: Westinghouse Electric Corp. Atomic Power Dept., Pittsburgh
• NSA Number: NSA-15-012596
• OSTI ID: 4076403
• Report Number(s): WCAP-1346
• Country of Publication: Country unknown/Code not available
• Language: English

Related Subjects

BARRIERS
BRAZING
CONTROL ELEMENTS
CONTROL SYSTEMS
CORROSION
CREEP
CVTR
FUEL ELEMENTS
IMPACT SHOCK
IRRADIATION
MAGNESIUM
MATERIALS TESTING
NEUTRONS
PRESSURE
REACTOR TECHNOLOGY
REACTORS
RODS
SEALS
SERVOMECHANISMS
SHIELDING
SHUTDOWN
SPACERS
TENSILE PROPERTIES
THERMAL CONDUCTIVITY
WELDING
WIRES
ZIRCALOY