E 1.99:ornl-3126
|
THE ORNL BADGE DOSIMETER AND ITS PERSONNEL MONITORING APPLICATIONS |
1 |
E 1.99:ornl-3127
|
REACTOR CHEMISTRY DIVISION ANNUAL PROGRESS REPORT FOR PERIOD ENDING JANUARY 31, 1961 |
1 |
E 1.99:ornl-3128
|
EVALUATION OF ULTIMATE DISPOSAL METHOD FOR LIQUID AND SOLID RADIOACTIVE WASTES. PART I. INTERIM LIQUID STORAGE |
1 |
E 1.99:ornl-3129
|
INLINE DENSIMETER FOR PULSED COLUMN LIQUID DENSITY, PULSE AMPLITUDE, AND PULSE FREQUENCY MEASUREMENTS |
1 |
E 1.99:ornl-3130
|
BARYTES CONCRETE FOR RADIATION SHIELDING MIX CRITERIA AND ATTENUATION CHARACTERISTICS. |
1 |
E 1.99:ornl-3131
|
IN-PILE LOOP CORROSION EXPERIMENTS WITH URANYL SULFATE SOLUTIONS AT 235 AND 250 C |
1 |
E 1.99:ornl-3132
|
POLFIT II, AN IBM 7090 PROGRAM FOR POLYNOMIAL LEAST SQUARES FITTING |
1 |
E 1.99:ornl-3139
|
SURFACE PREPARATION OF METALLOGRAPHIC SPECIMENS OF ZIRCONIUM-BASE ALLOYS CONTAINING COPPER |
1 |
E 1.99:ornl-3141
|
DETERMINATIONS OF THE KINETICS AND MECHANISMS OF DEBORONIZATION AT 1135 C |
1 |
E 1.99:ornl-3143
|
MISCELLANEOUS EXPERIMENTS RELATING TO THE PROCESSING OF CETR FUEL BY SULFEX- THOREX AND DAREX-THOREX PROCESSES |
1 |
E 1.99:ornl--3144
|
AIRCRAFT NUCLEAR PROPULSION PROJECT SEMIANNUAL PROGRESS REPORT for Period Ending April 30, 1961 |
1 |
E 1.99:ornl-3145
|
A STUDY OF FISSION PRODUCT TRANSPORT MECHANISMS IN HIGH TEMPERATURE GAS- COOLED REACTOR FUEL ELEMENTS |
1 |
E 1.99:ornl-3147
|
A SURVEY OF THE HAZARDS INVOLVED IN PROCESSING LIQUID METAL BONDED FUELS |
1 |
E 1.99:ornl-3148
|
STRUCTURE AND USE OF ALGOL 60 |
1 |
E 1.99:ornl-3150
|
WHIRLAWAY--A THREE-DIMENSIONAL, TWO-GROUP NEUTRON DIFFUSION CODE FOR THE IBM 7090 COMPUTER |
1 |
E 1.99:ornl-3151
|
THE CORROSION OF ALUMINUM ALLOYS IN THE OAK RIDGE RESEARCH REACTOR |
1 |
E 1.99:ornl-3152
|
RADIOACTIVITY OF NUCLEAR REACTOR COOLING FLUIDS |
1 |
E 1.99:ornl-3153
|
CHEMICAL TECHNOLOGY DIVISION ANNUAL PROGRESS REPORT FOR PERIOD ENDING MAY 31, 1961 |
1 |
E 1.99:ornl-3155
|
LABORATORY DEVELOPMENT OF THE ACID THOREX PROCESS FOR RECOVERY OF CONSOLIDATED EDISON THORIUM REACTOR FUEL |
1 |
E 1.99:ornl-3157
|
EXPERIMENTAL STRESS ANALYSIS OF EGCR PRESSURE VESSEL. PART 1. EXPERIMENTAL DETERMINATION OF STRESSES IN MODEL. PART 2. INTERPRETATION OF EXPERIMENTAL RESULTS AND EXAMINATION FOR STRUCTURAL INTERGITY |
1 |