Pathfinder Atomic Power Plant Technical Progress Report for October 1958-December 1958 PDF Download

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Category : Nuclear power plants
Languages : en
Pages : 88

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Book Description
Dynamic and static high-temperature water corrosion tests are reported for Al alloys such as X800l + Mg and 198X, Data are presented for one dynamic comparison test for these two alloys at pH 5.5 with H/sub 3/PO/sub 4/. End closures of type 3003(Al--1.2% Mn) and X8001(Al--1% Ni) made by spinning were pressure leak tested and examined microscopically. Results are tabulated, and photomicrographs are included. All tubes that were spun but not welded had cracks, however, the fusion welded tubes were more sound. Progress in design activities related to reactor mechanical features is reported, including an analysis of boiler pressure drop and void distribution, and the recirculation system piping. Data on forces and moments due to thermal expansion in the loops under four conditions of support; and flow restraint at the pump are tabulated. Test information and conclusions on the design of control rods and guide tubes are given. An analysis of individual constituents of reactivity coefficients was conducted with the emphasis on nuclear parameters such as the thermal neutron spectrum, thermal disadvantage factors, resonance escape probability, fast fission factor, and epithermal neutron age. The reactivity changes produced by variations in these parameters are tabulated. Data are also given on the isoflux line patterns in the 64 rod core section obtained from calculations of flux and power distribution effects at the superheater boiler core interface. Control rod heating due to radiation was calculated as 1.22 x 10/sup 6/BTU/ft/sup 3/-hr. Shielding design based on calculated activity buildup due mainly to crud is described, and one possible arrangement is considered in relation to the neutron and gamma flux. Reactor water purification design modification includes the addition of a booster pump under the flash tank to be used during reactor shut- down. Descriptiona of control rod programming and circuits are presented, and a list of abnormal conditions to be considered in the design of a safety alarm system is given. Procedures for obtaining power and period measurements are given as well as the design of a steam pressure control device and a water level control and measurement system. Other instrument design work is reported on shut- down pump controls, leak and rupture detection, various emergency valves, flash tank controls, water pressure controller, resin protection controls, and various hand operated valves. Feasibility studies on fuel element design, fuel materials such as UO/sub 2/--stainless steel cermets, thermal expansion tests, air flow tests for superheater fiow characteristics, and a cooling test are reported. Drawings and photographs related to materials and designs are included. (For preceding period see AECU-3910)