RESEARCH AND DEVELOPMENT PROGRAM QUARTERLY PROGRESS REPORT FOR THE PERIOD OCTOBER 1, 1959 TO DECEMBER 31, 1959

Technical Report · Mon Feb 01 04:00:00 EST 1960

OSTI ID:4141830

DeHuff, P G

Several changes were made in the pressure-tube design. The location of the Zircaloy-- stainless-steel transition joint was raised to an elevation higher on the pressure tabe to keep stainless steel out of the reflector region of the core. The statnless-steel portion of the pressure tube was changed from an assembly of three parts to an assembly of two parts. This was done by specifying that the stainless-steel legs be made completely from 410 stainless rether than 410 and 304 stainless as previously specified. The preparation of a thermal- cycling test facility was completed. Testing of gasketed fittings was initiated in this facility. The scheduled 2000 hr corrosion test on six control-rod materials was completed. The rolled Zircaloy-stainless-steel transition-joint design being developed by Canadian General Electric was selected as the prime alternate to the Marman Conoseal type of joint. Information received from Canadian General Electric indicated that the rolled joint appears to be very promising. Modifications were made to the thermal-baffle design, improving it and simplifying fabrication. The design of the top neutron shield was changed. The new design consists of alternate layers of heavy water and steel plates, the heavy water being obtained by raising the moderator level. To reduce the heat losses, a thermal baffle was provided around the neutron-streaming plug. However, even with this baffle, the heat loss to the moderator by conduction through the pressure-tabs walls increased from 1.9 to 2.6 Mw. A Zircaloy-2 fuel- assembly support grid was satisfactortly brazed. Attempts are being made to develop methods of bonding the spiral Zircaloy spacer wire to the fuel rods. Tests to determine the degree of coolant mixing in the fuel assemblies were started in the low-preesure loop. The tests to determine the pressure drop across the fuel assemblies are approximately 70% completed. Testing to determine pressure drop across the various proposed orifice designs was started. The failed-fuel-element detection system was thoroughly investigated to determine the circumstances under which defective fuel elements can be detected. (See also CVNA-30.) (auth)

• Research Organization: Westinghouse Electric Corp. Atomic Power Dept., Pittsburgh
• NSA Number: NSA-15-003668
• OSTI ID: 4141830
• Report Number(s): CVNA-45
• Country of Publication: United States
• Language: English

Related Subjects

BONDING
BRAZING
CONTROL ELEMENTS
COOLANTS
CORROSION
DETECTION
FUEL ELEMENTS
HEAT TRANSFER
HEAVY WATER
HEAVY WATER MODERATOR
IN PILE LOOPS
JOINTS
LEAKS
MIXING
NEUTRONS
PRESSURE
REACTOR CORE
REACTOR TECHNOLOGY
REACTORS
REFLECTORS
RODS
SEALS
SHIELDING
STAINLESS STEELS
TESTING
THERMAL INSULATION
TUBES
WIRES
ZIRCALOY
ZONES