NUCLEAR ENGINEERING DEPARTMENT LMFR BIMONTHLY PROGRESS REPORT FOR JANUARY- FEBRUARY 1959

Technical Report · Mon Apr 20 00:00:00 EST 1959

OSTI ID:4242107

A detailed study of the breeding potential of U/sup 233/ systems as a function of neutron spectrum was initiated. Analytical calculations of neutron capture in Bi resonances were completed. Final values of the buckling of the ''l9'' stack are 6.24 plus or minus 0.31 x 10/sup -4/ cm/sup -2/ (measured) and 6.36 x 10/sup -4/ cm/sup -2/ (calculated). Pulsed neutron measurements on GBF graphite gave results for the absorption cross section, transport mean free path, diffusion coefficient, and diffusion length. Ten materials were screened for corrosion resistance to a salt mixture consisting of 5% BiCl/sub 3/ in a ternary eutectic NaCl-KClMgCl/sub 2/. The behavior of different graphites toward Xe produced by irradiating U-Bi fuel was investigated. A ThO/sub 2/-Bi slurry containing 0.5 wt.% Mg was irradiated at 500 deg C for 5 months. The activity coefficient of Th in Bi was found to be 10/sup -9/ at 500 deg C, at infinite dilution. Further information was obtained about the electrochemistry of U/sup 3+/ in fused salts. A large number of ThO/sub 2/ powders was prepared by aqueous methods. The stability of ThC/sub 2/-Bi was tested by contacting a 7.3 wt. % mixture at 600 deg C. ThO/sub 2/-Bi slurries were produced on both gram and kilogram scales. The minimum additive requirements for dispersing 10 wt. % of both Norton 900F ThO/sub 2/ and Norton 60F ThO/sub 2/ in liquid Bi at 600 deg C are 0.000029 to 0.000037 g atoms Mg per g ThO/sub 2/ or 0.000012 to 0.000015 g atoms Zr per g ThO/sub 2/. The addition of 1 wt.% Mg to U-Zr-Bi alloys partially eliminates the reduction of U solubility in Bi containing Zr. The solubility or U in Bi is increased by Cs additions up to 1.5 wt.% Cs. The addition of Na to U- Bi alloys caused the U solubility to increase to maximum at 2 wt. % Na and then to decrease as the Na content was increased to 8 wt. % Na. A slurry of ThBi/sub 2/ in Bi containing 3.34 wt. % Th, 0.41 wt. % Te, and 317 ppm Zr was circulated in a 2 1/4 Cr-1 Mo steel loop at 1.5 ft/sec through a bulk temperature differential of 21 deg C (W4-465 deg C) for 1500 hr. Six new thermal convection loops were started to test the corrosion resistance of carbon steels and the effects of high maximum temperature and high temperature differential on corrosion of steels by inhibited Bi melts. Welding problems are discussed. Thermal conductivity measurements on irradiated graphites were made. Loop construction progress is summarized. ( See also BNL-4097.) (W.D.M.)

• Research Organization: Brookhaven National Lab., Upton, N.Y.
• NSA Number: NSA-13-016621
• OSTI ID: 4242107
• Report Number(s): BNL-4261
• Resource Relation: Other Information: Orig. Receipt Date: 31-DEC-59
• Country of Publication: United States
• Language: English

Related Subjects

REACTORS
ABSORPTION- CROSS SECTIONS- - DIFFUSION LENGTH- GBF GRAPHITE- GRAPHITE- MEASURED VALUES- NEUTRONS- PLANNING- POWER PLANTS- PULSE ANALYZERS- PULSES- REACTORS- TRANSPORT THEORY
ACTIVATION- BISMUTH- - FUEL SLURRIES- IRRADIATION- MAGNESIUM- PLANNING- POWER PLANTS- QUANTITY RATIO- REACTORS- SLURRIES- SOLUTIONS- THORIUM OXIDES
BISMUTH ALLOYS- FUELS- GRAPHITE- IRRADIATION- PLANNING- POWER PLANTS- REACTORS- URANIUM ALLOYS- XENON
BISMUTH CHLORIDES- CORROSION- EUTECTICS- MAGNESIUM CHLORIDES- MATERIALS TESTING- MIXING- PLANNING- POTASSIUM CHLORIDES- POWER PLANTS- REACTORS- SALTS- SODIUM CHLORIDES
BISMUTH- BIS