E 1.99:anl-7193
|
REACTOR DEVELOPMENT PROGRAM PROGRESS REPORT, MARCH 1966 |
1 |
E 1.99:anl--7194
|
GENERAL INPUT SPECIFICATIONS FOR ANL REACTOR PROGRAMS. |
1 |
E 1.99:anl--7195
|
DESIGN, CONSTRUCTION DETAILS, AND PREOPERATIONAL TESTING OF AN ARGONNE FAST CRITICAL FACILITY. |
1 |
E 1.99:anl-7196
|
MEASUREMENT OF BEAM PROFILES WITH THERMOLUMINESCENT DOSIMETERS |
1 |
E 1.99:anl--7197
|
GENERALIZED COMPUTER PROGRAM FOR FLOWSHEET CALCULATION AND PROCESS DATA REDUCTION. |
1 |
E 1.99:anl--7198
|
PHYSICS DIVISION SUMMARY REPORT, MARCH--APRIL 1966. |
1 |
E 1.99:anl--7199
|
COMPUTER PROGRAM FOR THE KINETIC TREATMENT OF RADIATION-INDUCED SIMULTANEOUS CHEMICAL REACTIONS. |
1 |
E 1.99:anl--7200
|
RATIONAL CHEBYSHEV APPROXIMATIONS FOR FERMI-DIRAC INTEGRALS OF ORDERS -1/2, 1/2, AND 3/2. |
1 |
E 1.99:anl--7201
|
EBR-II FUEL-UNLOADING MACHINE DESIGN AND PERFORMANCE CHARACTERISTICS. |
1 |
E 1.99:anl--7202
|
THE ELECTRICAL DESIGN OF THE EBR-II. |
1 |
E 1.99:anl--7203
|
HIGH CONVERSION CRITICAL EXPERIMENTS. |
1 |
E 1.99:anl--7203(add.)
|
ADDENDUM TO THE REPORT ON HIGH CONVERSION CRITICAL EXPERIMENTS. |
1 |
E 1.99:anl-7204
|
REACTOR DEVELOPMENT PROGRAM PROGRESS REPORT, APRIL 1966 |
1 |
E 1.99:anl--7205
|
DAUGHTER GROWTH IN FRESHLY SEPARATED ²²⁶Ra, ²²⁷Ac, AND ²³²U. |
1 |
E 1.99:anl--7206
|
VANADIUM ALLOY SCREENING STUDIES AND FABRICATION OF V--15 WT. PERCENT Ti-- 7.5 WT. PERCENT Cr TUBING FOR NUCLEAR FUEL CLADDING. |
1 |
E 1.99:anl--7208
|
ZPR-9 ASSEMBLIES NO. 6-9 CRITICAL EXPERIMENTS. |
1 |
E 1.99:anl-7209
|
AVERAGES OF INTERFEROMETRIC MEASUREMENTS OF THORIUM LINES |
1 |
E 1.99:anl--7212
|
EXPERIMENTAL BOILING-LIQUID-METAL FAST REACTOR. |
1 |
E 1.99:anl--7213
|
MULTISTEP INTEGER-PRESERVING GAUSSIAN ELIMINATION. |
1 |
E 1.99:anl--7214
|
HYDRODYNAMICS OF A NEW CONCEPT OF PRIMARY CONTAINMENT BY ENERGY ABSORPTION. |
1 |