Title: TEST OF ALLIS-CHALMERS CANNED ROTOR MERCURY PUMP

Tests were carried out to determine the operating characteristics of the 1D 2400-volt bus under various load conditions. The data indicated that the three-phase voltage was balanced during the five different bus load conditions and dropped from a no-load voltage of 2400 plus or minus 50 volts to 2300 plus or minus 50 volts under the worst load conditions. The voltage dropped to a minimum of 2200 plus or minus 50 volts during the time the 1D pump was accelerating to operating speed. Test data aIso indicated that the 1D 2400-volt bus three-phase currents and voltage were balanced and hadmore » sufficient capacity to start the lD reactor coolant pump under the most adverse bus load conditions. (M.C.G.)« less

Tests were run to determine the starting and operating characteristics of the Shippingport pressurized water reactor coolant pump under various loop conditions and pump configurations, after modifications and after the pump had been in a hot standby condition. (auth)

This report documents the current status of fabrication and assembly planning for the magnetic bearing, canned rotor pump being used as a demonstration platform for deeply integrating I&C into nuclear power plant components. The report identifies material choices and fabrication sequences for all of the required parts and the issues that need to be either resolved or accommodated during the manufacturing process. Down selection between material options has not yet been performed. Potential suppliers for all of the necessary materials have also been identified. The assembly evaluation begins by logically subdividing the pump into modules, which are themselves decomposed intomore » individual parts. Potential materials and fabrication processes for each part in turn are then evaluated. The evaluation process includes assessment of the environmental compatibility requirements and the tolerances available for the selected fabrication processes. A description of the pump power/control electronics is also provided. The report also includes exploded views of the modules that show the integration of the various parts into modules that are then assembled to form the pump. Emphasis has been placed on thermal environment compatibility and the part dimensional changes during heat-up. No insurmountable fabrication or assembly challenges have been identified.« less

The A-C Critical Facility Reactor will be used as an aid in the nuclear design of the CRBR. The reactor is cylindrical, heterogeneous, unpressurized, and water moderated. The core is composed of two regions, a superheater mockup in the center surrounded by an annular boiler region mockup. The fuel elements in the superheater region will be of fully enriched UO/sup 2/--stainless steel cermet, clad with stainless steel. The fuel elements in the boiler region will be slightly enriched UO/sub 2/ clad with Al. The most severe credible accident was found to be the startup accident. (W.D.M.)