NUCLEAR ENGINEERING DEPARTMENT PROGRESS REPORT FOR FEBRUARY 15-DECEMBER 31, 1956
Technical Report
·
OSTI ID:4344443
Studies of the statics and kinetics of Liquid Metal Fuel Reactor systems were continued. The effects of fluid compressibility, coolant channel size, and graphite penetrability were examined. Several salt-metal equilibrium experiments were carried out to determine partition coefficients for Ce in Bi--Ce --Mg and NaCl-KCl-- MgCl/sub 2/ systems, and for Nd in Bi--Mg--Nd and NaCl -KCl --MgCl/sub 2/ system. Data obtained on the variation of the activity coefficient of Mg in Bi with temperature were used to calculate partial entropy-of-solution values. The first compound in the Th--Bi system is now considered to be ThBi/sub 2/ instead of Th/sub 3/Bi/sub 5/. Studies were continued on the distribution of Pa and U between solid thorium bismuthide and liquid Bi and Pb--Bi eutectic alloy. Studies of steel corrosion in Bi--U alloys with various additives were continued. Uranium and fission products dissolved in Bi were contacted with graphite to observe possible reactions. No uranium carbide was formed, but some fission product reactions were detected. Measurements of the sorptive properties of various graphites for liquid Bi were continued in an effort to select the graphite for the LMFR. The construction of the continuous dissolver pilot plant for the fluoride volatility process was completed and testing was started. The four constituents of the dissolver stream will be analyzed as follows: UF/sub 6/ by volumetric analysis, BrF/sub 3/ and BrF/sub 5/ by refractive index, and Br by colorimetric determination. A conceptual design was completed for a maximum neutron leakage, indium sulfate reactor for use in a food irradiation facility. Startup data for the first enriched fuel element loaddng of the Brookhaven Reactor were obtadned. (For preceding period see BNL-418.) (D.E.B.)
- Research Organization:
- Brookhaven National Lab., Upton, N.Y.
- NSA Number:
- NSA-12-010011
- OSTI ID:
- 4344443
- Report Number(s):
- BNL-434
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
ABSORPTION-- BISMUTH-- GRAPHITE-- LIQUID METALS-- LMFR-- MEASURED VALUES-- REACTORS
BISMUTH ALLOYS-- COMPOUNDS- - THORIUM ALLOYS
BISMUTH ALLOYS-- CORROSION-- STEELS-- URANIUM ALLOYS
BISMUTH-- BISMUTH ALLOYS-- DISTRIBUTION-- LEAD ALLOYS-- LIQUID METALS-- PROTACTINIUM-- THORIUM ALLOYS-- URANIUM
BISMUTH-- CARBIDES-- CHEMICAL REACTIONS-- FISSION PRODUCTS-- GRAPHITE-- LIQUID METALS-- SOLUTIONS-- URANIUM-- URANIUM COMPOUNDS
BISMUTH-- CERIUM-- DISTRIBUTION-- MAGNESIUM-- MAGNESIUM CHLORIDES-- MEASURED VALUES-- METALS-- MIXING-- POTASSIUM CHLORIDES-- SALTS-- SODIUM CHLORIDES-- SOLVENTS
BISMUTH-- ENTROPY-- MAGNESIUM-- NUMERICALS-- SOLUTIONS-- TEM
PHYSICS
BISMUTH ALLOYS-- COMPOUNDS- - THORIUM ALLOYS
BISMUTH ALLOYS-- CORROSION-- STEELS-- URANIUM ALLOYS
BISMUTH-- BISMUTH ALLOYS-- DISTRIBUTION-- LEAD ALLOYS-- LIQUID METALS-- PROTACTINIUM-- THORIUM ALLOYS-- URANIUM
BISMUTH-- CARBIDES-- CHEMICAL REACTIONS-- FISSION PRODUCTS-- GRAPHITE-- LIQUID METALS-- SOLUTIONS-- URANIUM-- URANIUM COMPOUNDS
BISMUTH-- CERIUM-- DISTRIBUTION-- MAGNESIUM-- MAGNESIUM CHLORIDES-- MEASURED VALUES-- METALS-- MIXING-- POTASSIUM CHLORIDES-- SALTS-- SODIUM CHLORIDES-- SOLVENTS
BISMUTH-- ENTROPY-- MAGNESIUM-- NUMERICALS-- SOLUTIONS-- TEM
PHYSICS