LIQUID METAL FUEL REACTOR EXPERIMENT QUARTERLY TECHNICAL REPORT FOR APRIL 1958-JUNE 1958

Technical Report · Mon Oct 31 00:00:00 EST 1960

OSTI ID:4167092

5 6 : 4 : 6 6 : 6 5 6 7 6 engineering, chemistry, materials and inspection and in reactor kinetics were continued. Activities in these areas are summarized. Preparation of spectrographic standards for chemical analyses included several new procedures for the purification of bismuth to decrease iron, and chromium. Analytical work for various LMFRE tests included 1,641 separate determinations on 307 samples. Mercury and mercury vapor procedures were used in the cleaning of specimens, components, and a bismuth test loop. Contract work on uranium solubility was completed and a report is being written. The test apparatus for sodium-bismuth leak testing has been completed and the size of the controlled leak was calibrated using water. Results of corrosion work in the dynamic test loops showed the value of the zirconium additive in reducing corrosion. Improvements to the loops have reduced cold locations which could collect uranium and reduce loop concentrations. Corrosion of hot zones and metal transport of the loop material to cold areas have been noted, particularly on the loops with low zirconium concentration. Capsule testing has shown metal transport and corrosion at the higher temperatures under which this screening test has been operating. In addition to Croley 21/4 and 11/4 the capsules inoluded beryllium, tantalum, and other alloys, preparatory to use in test loops. The initial stressruptare and creep information on Croloy 21/4 and 11/4 in liquid bismuth fuel aolutions compares well with that in an air atmosphere. Impact data at operating temperature show an improvement after aging. The outgassing of graphite has began and other graphite projects have been discussed. Graphite seals and weepage tests await receipt of specimens. Preparation of graphite pellets with impregnant materials included, indicates that aubsequent oxidation to form the metal oxides will be difficult. The formation of carbides appears promising and is now under investigation. Design of apparatus and test procedures for checking instrumentations for temperature, pressure, liquid level, and flow is complete. Most of the apparatus is complete and tests will begin as prototype instruments are received. Work on the prototypes of various components is very active. Beryllium is on hand and dry box equipment and other health safety requirements are being prepared for development of the "thimble." The 21/2 in. test loop for the testing of valves and other components is almost complete. Initial induction heating tests indicated exoessive gradients, and revisions are now being tested. Test apparatus for cavitatibn and for new projects on the testing of valves, filters, and bellows are complete in most cases and await receipt of specimens for the initial proof tests. A sparging device tested with water and mercury is being placed in the first in-pile test loop. Assembly of the in-pile loop for the ETR reactor is almost complete. The inpile section for the critical facility test as Arco has been shipped. Design of loop No. 3 (MTR) is almost complete and construction of components is underway. The investigation of welding procedures for remote operation has produced successful welds on 21/2-in. OD x 0.250-in. wall and 65/8-in. OD x 0.313-in. wall steels. Additional work is underway on other sizes and with tubing on which a bismuth filin remains from operation. The consumable arc, gas-shielded welding process has been discontinued. The Engineering Prototype Development Facility was leased and renovated for the developmental testing of LMFRE-I maintenance equipment and operational mechanisms. The first drnft of a maintenance reference design report has been prepared and released. This report elaborates upon functions of maintenance equipment, more fully explains techniques and procedures to be utilized in typical plant maintenance

• Research Organization: Babcock and Wilcox Co. Atomic Energy Div., Lynchburg, Va.
• DOE Contract Number: AT(30-1)-1940
• NSA Number: NSA-14-015448
• OSTI ID: 4167092
• Report Number(s): BAW-1116
• Resource Relation: Other Information: Orig. Receipt Date: 31-DEC-60
• Country of Publication: United States
• Language: English

Related Subjects

REACTOR TECHNOLOGY
BERYLLIUM
BERYLLIUM ALLOYS
BISMUTH
CARBIDES
CHROMIUM
CHROMIUM ALLOYS
CLEANING
COOLANT LOOPS
CORROSION
CREEP
CRITICALITY
CROLOY
DEGASSING
DISPERSIONS
FABRICATION
FILTERS
FUEL SLURRIES
GRAPHITE
HIGH TEMPERATURE
IMPREGNATION
IMPURITIES
IN PILE LOOPS
INSTRUMENTS
IRON
LEAKS
LEVELS
LIQUID FLOW
LIQUID METAL FUEL
LMFR
MAGNESIUM
MAINTENANCE
MECHANICAL PROPERTIES
MERCURY
MULTIPLICATION FACTORS
OPERATION
OXIDES
PELLETS
PLANNING
PREPARATION
PRESSURE
QUALITATIVE ANALYSIS
REACTIVITY
REACTORS
REDUCTION
REMOTE HANDLING
SEALS
SELENIUM
SOLUBILITY
SPECTROSCOPY
STABILITY
STAINLESS STEELS
STANDARDS
STEELS
STRES