E 1.99:tid-17254
|
PERFORMANCE OF CESIUM THERMIONIC DIODES OPERATED IN SERIES-PARALLEL CIRCUITS |
1 |
E 1.99:tid-17306
|
APPLICATION OF NUCLEAR POWER SUPPLIES TO SPACE SYSTEMS |
1 |
E 1.99:tid-17402
|
HIGH TEMPERATURE CLADDING ALLOYS FOR REACTOR APPLICATIONS |
1 |
E 1.99:tid-17478
|
ZIRCALOY PICKLE BATH SALTS. CHEMICAL NATURE AND THERMAL DECOMPOSITION OF HYDRATED ZIRCONIUM FLUORIDE |
1 |
E 1.99:tid-17706
|
NUCLEAR TECHNOLOGY DATA FOR SM-1, SM-1A, PM-2A, SM-2 |
1 |
E 1.99:tid--18065
|
Flow Phenomena in Rapidly Rotating Systems |
1 |
E 1.99:tid-18098
|
TEMPERATURE DISTRIBUTION MODERATOR AND REFLECTOR REACTOR CORE. EXPERIMENTAL GAS COOLED REACTOR |
1 |
E 1.99:tid-18100
|
COOLANT FLOW DISTRIBUTION PERMEATION OF COOLANT THROUGH GRAPHITE |
1 |
E 1.99:tid-18238
|
TEMPERATURE DISTRIBUTION, MODERATOR AND REFLECTOR REACTOR CORE |
1 |
E 1.99:tid-18243
|
RADIAL FAST NEUTRON LEAKAGE FROM EXPERIMENTAL GAS COOLED REACTOR |
1 |
E 1.99:tid-18244
|
DESIGN AND ANALYSIS CORE STRUCTURE AND BOTTOM PLATE. |
1 |
E 1.99:tid-18245
|
THERMAL AND TOTAL EPITHERMAL NEUTRON FLUX DISTRIBUTIONS IN THE EXPERIMENTAL GAS COOLED REACTOR |
1 |
E 1.99:tid-18251
|
ANALYSIS--GRAPHITE CORE STRUCTURE |
1 |
E 1.99:tid-18290
|
SEPARATION OF TECHNETIUM-99 FROM URANIUM HEXAFLUORIDE |
1 |
E 1.99:tid-18299
|
ORGANOPHOSPHORUS COMPOUNDS, OTHER THAN TBP, FOR PROCESSING OF IRRADIATED FUELS AND BY-PRODUCTS |
1 |
E 1.99:tid--18314
|
Control rod drive system description and design criteria |
1 |
E 1.99:tid-18323
|
RADIOISOTOPE-FUELED POWER SUPPLIES. Lecture Presented at University of California, Los Angeles, California, UCLA Short Course, Space Power Systems, July 17-28, 1961 |
1 |
E 1.99:tid-18430
|
ON DISPERSION STRENGTHENING OF ZIRCONIUM |
1 |
E 1.99:tid-18474
|
HIGH ACCELERATION FIELD HEAT TRANSFER FOR AUXILIARY SPACE NUCLEAR POWER SYSTEMS. Quarterly Technical Report, December 1, 1962-February 28, 1963 |
1 |
E 1.99:tid-18558
|
NUCLEAR PROPULSION--AN EMERGING TECHNOLOGY |
1 |