Call Number (LC) Title Results
E 1.99:bmi-1640 USE OF AGGLOMERATED UO$sub 2$ IN PRESSURE-BONDED STAINLESS STEEL-CLAD FUEL RODS 1
E 1.99:bmi-1664 A STUDY OF THE TENSILE FRACTURE AND MICROSTRUCTURE OF URANIUM 1
E 1.99:bmi-1685 CONSTITUTION OF THE SYSTEMS OF URANIUM AND CARBON WITH MOLYBDENUM, NIOBIUM, RHENIUM, TUNGSTEN, AND YTTRIUM 1
E 1.99:bmi-1689 STUDIES IN THE UO₂-ZrO₂ SYSTEM 1
E 1.99:bmi-1698 AN EVALUATION OF PLUTONIUM COMPOUNDS AS NUCLEAR FUELS 1
E 1.99:bmi--1714 High-temperature thermal propeties of SNAP-10A fuel material 1
E 1.99:bmi-1730 High-temperature irradiation of niobium-1 w/o zirconium-clad UO₂. [Compatibility with lithium] 1
E 1.99:bmi-1740 Phase I summary report on the development of segmented thermoelectric modules. [Bi₂Te₃ and PbTe] 1
E 1.99:bmi--1786 DEVELOPMENT OF SEGMENTED THERMOELECTRIC MODULES. Phase 2 Summary Report. 1
E 1.99:bmi--1787 INVESTIGATION OF TRITIUM GENERATION AND RELEASE IN PM NUCLEAR POWER PLANTS. 1
E 1.99:bmi-1789 Thermal stability of zirconia-s and thoria-base fuels (LWBR Development Program) 1
E 1.99:bmi--1806 Irradiation behavior of uranium monocarbide. Task No. 6 1
E 1.99:bmi--1808 DESIGN OF A CAPSULE FOR IRRADIATION NEAR 2000 C. 1
E 1.99:bmi--1852 Recent Developments in Reactor Materials Technology 1
E 1.99:bmi--1886 URANIUM--PLUTONIUM NITRIDE FUELS FOR LMFBR APPLICATIONS.
PROGRESS ON DEVELOPMENT OF FUELS AND TECHNOLOGY FOR ADVANCED REACTORS DURING JULY 1969--JUNE 1970. Annual Report. 		2
E 1.99:bmi--1889 STUDIES OF THE EFFECTS OF IRRADIATION ON CLADDING AND STRUCTURAL ALLOYS.
PROGRESS ON LMFBR CLADDING, STRUCTURAL, AND COMPONENT MATERIALS STUDIES DURING JULY 1969--JUNE 1970. Annual Report. 		2
E 1.99:bmi--1893 PROGRESS ON DEVELOPMENT OF FUELS AND TECHNOLOGY FOR ADVANCED REACTORS DURING JULY--SEPTEMBER 1970. Progress Report. 1
E 1.99:bmi--1898 PROGRESS ON DEVELOPMENT OF FUELS AND TECHNOLOGY FOR ADVANCED REACTORS DURING OCTOBER--DECEMBER 1970. Progress Report. 1
E 1.99:bmi--1901 SURVEY OF LMFBR COMPONENT MATERIALS, LIMITATIONS AND REQUIREMENTS. 1
E 1.99:bmi--1910 Evaluation of the applicability of existing data to the analytical description of a nuclear-reactor accident core meltdown evaluation. Topical Report, Task 18. 1