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LIQUID METAL FUEL REACTOR EXPERIMENT QUARTERLY TECHNICAL REPORT FOR OCTOBER-DECEMBER 1958

Technical Report ·
OSTI ID:4179431
Results of parametric calculations based on the established core design are given as graphs of K/sub eff/ vs. core height; void fraction; absorption cross sections for U/sup 235/, Bi, and graphite; Bi volume fraction in core and end reflector; and end reflector poison; multiplication constant vs. plenum thickness; ring worth of 8 B/sub 4/C rods vs. position in end reflector; critical Pu concentration vs. enrichment; and Th to U ratio criticality vs. fuel concentration. Brief reports are given of thermal and nuclear analysis and in strument and control development. The various LMFRE systems are described including primary coolant, intermediate coolant, heat rejection, electrical, ventilation, fuel addition and sampling, and waste disposal, The flyingrope bridge crane which has motors and gear train drives mounted stationary, not on the bridge, is described. Analytical procedures to detect impurities and minor constituents in bismuth are still under development. A suitable method of analysis for ETR samples is being emphasized and closely correlated with personnal from the NRTS Chemical Processing Plant, Chemical solvents used for decontamination have been checked for corrosive attack on Croloy 2 1/4. The corrosion rates appear satisfactory, being comparable to rates obtained using commercial acidcleaning techniques. Slurry work has confirmed the reduction of UO/sub 2/ by Zr, but no measurable reduction occurred in homogeneous thonia- urania particles. Work on reduction of uranium carbides and fluorides is also underway, in addition to wetting angle studies. Additional study of fuel solutions by metallurgical techniques has shown that uranium is not entirely in solution at the power operating temperatures; instead, it is present as extremely small paricles. Work on diaphragms, thermocouples, pressure indicators, level indicators, and flowmeters is underway. An electrical analog is being used in the study of electromagnetic flowmeters. The 2 1/2-in. test loop was completed; operation will begin after the level indicators and other test components are installed, A 10-gpm electromagnetic pump is being developed. Testing of a prototype bismuth pump in a 6-in. test loop was halted at request of the Atomic Energy Commission. The drybox and the glovebox were constructed to provide necessary facilities for beryllium welding. Preliminary welds were made in beryllium tubing to form a closed end "thimble," Investigation of brazing was begun. Several techniques were used to weld and braze molybdenum. Croloy 2 1/4 in small pipe sizes were induction welded. All of these projects showed encouraging results, The operation of dynamic pump test loops continued; some Croloy materials tests with the higher zirconium concentrations indicate satisfactory corrosion resistance. The tilting capsule tests indicate much greater corrosion and metal transport at 975 deg F but are beginning to show some advantage for Croloy 1 1/4. Several stress-rupture tests in a bismuth atmosphere were operating for over a year with very satisfactory results. Tensile, compressive, and shear strength testing of cemented graphite joints indicates that the joints are almost as strong as the base material. Tests on various graphite impregnants are reported. Preliminary absorption data and some density data are reported for various types of graphite. Physical and mechanical properties of graphite are being determined. Medulus of elasticity and flexural strength are also being determined. (For preceding period see BAW-1125.) (T.R.H.)
Research Organization:
Babcock and Wilcox Co. Atomic Energy Div., Lynchburg, Va.
NSA Number:
NSA-14-017595
OSTI ID:
4179431
Report Number(s):
BAW-1135
Country of Publication:
United States
Language:
English