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U.S. Department of Energy
Office of Scientific and Technical Information

LIQUID METAL FUEL REACTOR EXPERIMENT QUARTERLY TECHNICAL REPORT, JANUARY- MARCH 1959

Technical Report ·
OSTI ID:4226600
Preparation of a technical and economical evaluation for the first large- scale reference LMFR Plant is reported. Selection of optimum economic factors is described along with contaimnent and safety, maintenance aspects, and fuel characteristics. Reference plant arrangements are shown in drawings. Basic studies on carbides and oxides of U and Th were continued. Data are included on the dispersion of UC and ThC -- UC in Bi plus 700 to 800 ppm Zr. Solid solution ThO/sub 2/-UO/sub 2/ particles were tested in tilting capsules. Results showed that about 2% of the UO/sub 2/ was reduced to U after 1445 hr at 750 to 950 deg F. Bench scale loop tests of ThO/sub 2/--UO/sub 2/ dispersed in Bi are reported in which the slurry was circulated at 900 deg F; data and observations are tabulated. The current status of dynamic corrosion testing is tabulated. The ETR in-pile corrosion loop was operated for 1400 hr at 775 to 910 deg F. Generally, the loop operated satisfactorily, however several deficiencies were observed. These are listed and discussed. Tests for comparison of Croloy 11/4 and 21/4 reactions under similar conditions in liquid metal are reported. Croloy 11/4 appears superior in resistance to mass transfer. Experimests are being initiated to examine the formation of a nitride film on Zr used in Bi. Elements which may reduce the N availability to Zr are being examined. Data on the reactions of Croloy 21/4 with N as a function of temperature are presented. Data on mechanical properties of Croloy steels in Bi plus Zr, U, and Mg at 885 to 975 deg F are tabulated, and data on graphite for use in LMFRE are given. Aluminum carbide preparation by graphite impregnation is reported and data on graphite pore volume fllled with Al in this operation are given. Analog simulation work on the primary system was continued. The IHX analysis was completed and results were checked against analog data. Graphs of data show agreement in the variable transfer function. Cavitation parameter studies in which pure Bi is being used in the rotating disk are reported. Tests indicate a correlation between static pressure, and the distance of the damaged area from the disk's holes. Revision of the flow path to remove sharp turns in the LMFRE cooling system is reported. Progress in design of nonnuclear instrumentation, valves and bellows and small and large components is reported. Design and development of remote maintenance facilities such as remote viewers, control room, and remote welding equipment are discussed. (For preceding period see BAW-1135.) (J.R.D.)
Research Organization:
Babcock and Wilcox Co. Atomic Energy Div., Lynchburg, Va.
NSA Number:
NSA-13-023103
OSTI ID:
4226600
Report Number(s):
BAW-1152
Country of Publication:
United States
Language:
English