E 1.99:ornl-3032
|
A DEVICE TO SIMULATE THE SERVICE THERMAL CONDITIONS IN EGCR-TYPE FUEL ELEMENTS |
1 |
E 1.99:ornl-3033
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ELECTROMAGNETIC PRODUCTION OF PION PAIRS |
1 |
E 1.99:ornl-3037
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EFFECT OF ENERGY DEGRADATION ON THE CRITICAL CURRENT IN AN OGRA-TYPE DEVICE |
1 |
E 1.99:ornl-3039
|
REVIEW AND CORRELATION OF IN-PILE ZIRCALOY-2 CORROSION DATA AND A MODEL FOR THE EFFECT OF IRRADIATION |
1 |
E 1.99:ornl-3040
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EXACT RELATIVISTIC FOKKER-PLANCK COEFFICIENTS FOR A PLASMA |
1 |
E 1.99:ornl-3041
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SDC-A SHIELDING-DESIGN CALCULATION CODE FOR FUEL-HANDLING FACILITIES |
1 |
E 1.99:ornl-3042
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RESONANCE SCATTERING OF LINEARLY POLARIZED GAMMA RAYS ON NUCLEI |
1 |
E 1.99:ornl-3043
|
KINETICS OF THE CATALYZED OXIDATION OF HYDROGEN, CARBON MONOXIDE, AND METHANE BY OXYGEN IN A FLOWING STREAM OF HELIUM |
1 |
E 1.99:ornl-3045
|
McCABE-THIELE GRAPHICAL SOLUTION OF URANIUM-THORIUM PARTITIONING FROM 30% TBP-AMSCO SOLVENT |
1 |
E 1.99:ornl-3046
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MARITIME REACTOR PROJECT ANNUAL PROGRESS REPORT FOR PERIOD ENDING NOVEMBER 30, 1960 |
1 |
E 1.99:ornl-3047
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ELECTRONUCLEAR RESEARCH DIVISION ANNUAL PROGRESS REPORT FOR PERIOD ENDING MARCH 1, 1960 |
1 |
E 1.99:ornl-3049
|
GAS-COOLED REACTOR PROJECT QUARTERLY PROGRESS REPORT FOR PERIOD ENDING DECEMBER 31, 1960 |
1 |
E 1.99:ornl-3051
|
PLUTONIUM EXTRACTION FROM NITRATE AND SULFATE SOLUTIONS BY AMINES AND ORGANOPHOSPHORUS COMPOUNDS |
1 |
E 1.99:ornl-3053
|
STATUS REPORT ON WASTE DISPOSAL IN NATURAL SALT FORMATIONS PART III. |
1 |
E 1.99:ornl-3054
|
THE STRUCTURE OF AN ALGOL TRANSLATOR |
1 |
E 1.99:ornl-3055
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RECOVERY OF Np-237 BY AN OXIDATION-REDUCTION FLUORIDE PRECIPITATION METHOD |
1 |
E 1.99:ornl-3056
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EFFECT OF HEAT FLUX ON THE CORROSION OF ALUMINUM BY WATER. PART II. INFLUENCE OF WATER TEMPERATURE, VELOCITY, AND pH ON CORROSION-PRODUCT FORMATION |
1 |
E 1.99:ornl-3057
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THE DEAMINATION AND REARRANGEMENT OF ERYTHRO-1-AMINO-1-PHENYL-2-O-TOLYL-2- PROPANOL (THESIS) |
1 |
E 1.99:ornl-3058
|
PERSONAL RADIATION MONITOR |
1 |
E 1.99:ornl-3059
|
DEVELOPMENT OF NONDESTRUCTIVE TESTS FOR THE EXPERIMENTAL GAS-COOLED REACTOR FUEL ELEMENT |
1 |