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Title: NUCLEAR ENGINEERING DEPARTMENT PROGRESS REPORT FOR JANUARY 1-APRIL 30, 1959

Technical Report ·
OSTI ID:4170373

B ; ? 7 5 9 > 9 ; F > ; 9 F activity coefficient for Th in dilute Bi solutions at 500 deg C was found to be 3.3 x 10/ sup -9/ by the galvanic cell technique. In similar experiments, preliminary measurements suggest that the free energy of formation of ThC/sub 2/ is about -- 32 kcal/ mole at 780 deg C. In LMFR, the extent to which Sm adsorbs on core graphite was investigated. A potentiometric titration method was developed for the determination of small concentrations of U/sup +++/ in chloride melts. On the basis of preliminary results, there appears to be a considerable mutual solubility effect between Zr and Ru in Bi solutions. Salt Corrosion Studies. Sixteen different metals and alloys have been tested in rocking-furnace experiments to determine their suitability for constructing fuel-salt extraction columns. Removal of Fission Products Volatile. The behavior of fission product iodine and xenon in LMFR fuel systems was studied. Insoluble Slurry Work. In in- pile experiments it was indicated that appreciable adsorption of fission gases on ThO/sub 2/ particles dispersed in Bi may occur and present an operational problem. Metallurgy. ThBi/sub 2/ particle growth inhibition by Te results in an increased viscosity of an as-prepared ThBi/sub 2/-Bi slurry because of the greater number of particles <10 mu in diameter. Fluidity can be increased by heat treatment. The minimum amounts of Mg or Zr required to disperse ThO/sub 2/ powder appear to be independent of the ThO/sub 2/ mass and particle surface area. A reaction is indicated with an unknown impurity present in the Bi to approx equal 6 x 10/sup -6/ gram equivalent weights per g Bi. Mg and Zr additives lower the contact angle between ThO/sub 2/ and liquid Bi and improve wetting of the ThO/sub 2/ powder. At present corrosion of the welds appears to be the principal difficulty with respect to LMFR container materials. Experiments have shown that nitrogen in steels combined as AlN is not available for film formation. ZrN films can spall in areas where they are thickest, and can be reformed on these areas. The corrosion resistance of a 2 1/4 Cr-- 1 Mo steel decreases as its carbon content decreases below 0.10%. The low C content of weld rod metal coupled with C and Cr segregation during welding may be responsible for the preferential attack observed. The addition of 1 wt.% Mg in Bi partially eliminates the reduction in the solubility of U caused by Zr. The addition of 1.5 wt.% Cs increases the solubility of U in Bi by 25 to 50% between 400 deg and 500 deg C. A maximum in the solubility of U th Bi containing 2 wt.% Na was found at 400 deg to 500 deg C. The solubility of Zr in Pb-Bi alloy (Pb/Bi = 1.04) was found to be more than 10 times lower than in Bi. Zr in Bi has a mutual solubility product relation with Rh and Ru. Reactor Theory. Several studies in support of the design of the BNL high flux epithermal reactor were completed. Neutron spectra were calculated for water containing various concentrations of boron. Calculations were completed of resonance capture in 0.6-in.-diam uranium rods in water. A statistical evaluation of fission product absorption cross sections was completed. Eperimental Reactor Physics. The final value of the buckling of the "19" stack was measured and was found to be (6.24 plus or minus 0.31) x l0/sup -4/cm/sup 2/ . Reactor Evaluation and Advanced Design. Work continued on organic cooled reactor systems. Work was initiated and completed on a study of organic reactors for maritime use. Heat Transfer. Heat transfer coefficients, under improved test conditions, have been measured for parallel flow of Hg through staggered tube banks. Fluoride Volatility . Development studies continued on the nonaqueous NO/sub 2/-HF system for reprocessing fuel elements. Short-term Monel corrosion rates for a complete processing cycle involving dissolution, evaporation, drying of the salt, and opening of the system to the atmosphere have been as high as 10 mils/month at 400 deg F. The dissolution of sintered ThO/sub 2/ in NO/sub 2/-HF solution was not successful. In further work on the extraction of Pa/sup 233/ from irradiated ThF/sub 4/ powder, a series of semicontinuous

Research Organization:
Brookhaven National Lab., Upton, N.Y.
NSA Number:
NSA-14-008325
OSTI ID:
4170373
Report Number(s):
BNL-571
Resource Relation:
Other Information: Orig. Receipt Date: 31-DEC-60
Country of Publication:
United States
Language:
English