A representative cross section of the literature on the disposal of geothermal brine was perused and some of the general information and concepts is summarized. The following sections are included: disposal statistics--Texas Railroad Commission; disposal statistics--Louisiana Office of Conservation; policies for administering salt water disposal operations; salt water disposal experience of Gulf Coast operators; and Federal Strategic Petroleum Reserve Program's brine disposal operations. The literature cited is listed in the appended list of references. Additional literature is listed in the bibliography. (MHR)

The MOXY/SCORE computer program has been used to evaluate the influence of crossflow and radiation heat transfer on LOFT cladding temperatures during the blowdown phase of L2-4. The results of this study indicate that the radiation heat flux is responsible for 100 K reduction of peak cladding temperature during blowdown. They also indicate that, if the boundary conditions are specified uniformly over upper and lower plenums, the crossflow will be responsible for another 25 K reduction of peak cladding temperature during blowdown.

The LOFT Modular Drag Disc Turbine Transducer (MDTT) springs (for range 2, rhoV/sup 2/ = 4900 lbm/ft-sec/sup 2/) were analyzed to determine the static rhoV/sup 2/ load needed to cause a buckling failure. The static load needed to cause elastic buckling was found to be equivalent to a rhoV/sup 2/ value of 431,000 lbm/ft-sec/sup 2/ according to classical buckling theory, but could be as low as rhoV/sup 2/ = 100,000 lbm/ft-sec/sup 2/ due to uncertain end fixity and other spring imperfections.

The techniques used to evaluate the beam-current requirements for MFTF are similar to those in previous studies but incorporate some improvements. In particular, we have enlarged the radial code BUILDUP to allow for a smaller radial grid and to improve the numerical accuracy; we have also improved the model of the atomic physics processes and the particle-equilibrium calculations. Also, a model of plasma containment that conserves energy as well as particles but does not include any effect of the expected drift-cyclotron loss-cone (DCLC) turbulence has been incorporated into the previous studies. We show that the DCLC turbulence increases the average ion energy and decreases the particle confinement time. Because these effects cancel to first order, the beam-current requirements are independent of the turbulence. We find that 24 of the present LBL source modules would sustain a plasma with an average beta of 0.46. This figure is within 10% of the MFTF goal and is within our calculational accuracies. We further show that the beam-current requirements for the large-diameter plasma are consistent with those of experiments to study the buildup of a field-reversed plasma.

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The overall test program includes pump assembly, installation, testing, removal from the test loop, disassembly and final inspection of the entire pump. Testing will include checkout tests, head/flow and efficiency characterizations at selected speeds and sodium temperatures, suction performance determination, a 2000 hour design point endurance test, a 300 hour off design endurance test, and thermal transient tests. The pump will be cleaned of sodium, disassembled, and examined before the 2000 hour endurance test and after the thermal transient tests to determine the effects that long-term operation at 200 percent NPSH margin and off design operation at the same flow and NPSH have on the pump components.

The overall test program includes pump assembly, installation, testing, removal from the test loop, disassembly and final inspection of the entire pump. Testing will include checkout tests, head/flow and efficiency characterizations at selected speeds and sodium temperatures, suction performance determination, a 2000 hour endurance test, and thermal transient tests. The pump will be cleaned of sodium, disassembled, and examined before the 2000 hour endurance test and after the thermal transient tests to determine the effects that long-term operation at 200 percent NPSH margin has on the pump components. The testing will be done at Energy Technology Engineering Center (ETEC). Assembly, sodium removal, disassembly, and initial inspection will be performed at Component Handling and Cleaning Facility (CHCF) and sodium testing will be done at Sodium Pump Test Facility (SPTF).