Call Number (LC) Title Results
E 1.99:anl-5429 REMOVAL OF HALOGENS, CARBON DIOXIDE, AND AEROSOLS FROM AIR IN A SPRAY TOWER 1
E 1.99:anl-5430 CORROSION RESISTANT ALUMINUM ABOVE 200 C 1
E 1.99:anl-5431 ISOTOPES PRODUCTION REACTOR--SUMMARY OF COMPLETE DESIGN 1
E 1.99:anl-5437 UNIVAC PROGRAMS FOR THE SOLUTION OF ONE-DIMENSIONAL MULTIGROUP REACTOR EQUATIONS 1
E 1.99:anl-5441 THE BEHAVIOR OF URANIUM, THORIUM, AND OTHER SELECTED MATERIALS IN BROMINE TRIFLUORIDE, BROMINE PENTAFLUORIDE, CHLORINE TRIFLUORIDE, AND FLUORINE AT ELEVATED TEMPERATURES 1
E 1.99:anl-5442 CASTING URANIUM-5 w/o ZIRCONIUM-1.5 w/o NIOBIUM ALLOYS INTO ZIRCONIUM AND ZIRCALOY-2 CONTAINERS 1
E 1.99:anl-5449 ATTACK ON MATERIALS BY LEAD AT 1000 C 1
E 1.99:anl-5452 DESIGN STUDY OF A NUCLEAR POWER PLANT FOR 100-KW ELECTRIC AND 400-KW HEAT CAPACITY 1
E 1.99:anl-5453 EFFICIENCY STUDIES OF A HIGH-EFFICIENCY, HIGH-TEMPERATURE FILTER AGAINST FRESHLY GENERATED URANIUM OXIDE FUME 1
E 1.99:anl-5457 A PRELIMINARY NUCLEAR DESIGN STUDY OF DIPHENYL MODERATED AND COOLED REACTORS 1
E 1.99:anl-5461 REACTOR ENGINEERING DIVISION QUARTERLY REPORT ON THE POWER REACTOR PROGRAM FOR JANUARY 1, 1955 THROUGH MARCH 31, 1955 1
E 1.99:anl-5462 REACTOR ENGINEERING DIVISION UNCLASSIFIED QUARTERLY REPORT FOR JANUARY 1, 1955 THROUGH MARCH 31, 1955 1
E 1.99:anl-5465(del.) METALLURGY DIVISION QUARTERLY REPORT FOR APRIL, MAY, AND JUNE 1955 1
E 1.99:anl-5466 CHEMICAL ENGINEERING DIVISION SUMMARY REPORT FOR APRIL, MAY, AND JUNE 1955 1
E 1.99:anl-5471 REACTOR ENGINEERING DIVISION QUARTERLY REPORT FOR APRIL 1, 1955 THROUGH JUNE 30, 1955. SECTION II 1
E 1.99:anl-5472 NEUTRON-INDUCED DISCOMPOSITION OF GRAPHITE 1
E 1.99:anl-5475 THERMIONIC PROPERTIES OF URANIUM WIRE 1
E 1.99:anl-5477 EFFECTS OF IRRADIATION ON CAST SPECIMENS OF URANIUM-CHROMIUM EUTECTIC ALLOY. Final Report-Metallurgy Program 6.1.17 1
E 1.99:anl-5480 MEASUREMENT OF DELAYED NEUTRON YIELDS IN PLUTONIUM, URANIUM-233, URANIUM- 238, AND THORIUM RELATIVE TO YIELD IN URANIUM-235 1
E 1.99:anl-5481 THE HYDROLYSIS OF THE COMPOUND OF POTASSIUM WITH IRRADIATED GRAPHITE 1