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E 1.99:in--1017
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COMPUTER CODE FOR THE CALCULATION OF FUEL AND POISON CROSS SECTIONS FROM REACTIVITY MEASUREMENTS. |
1 |
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E 1.99:in--1018
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A STUDY OF THREE METHODS FOR REPROCESSING GRAPHITE FUELS MIXED ACID OXIDATION, GRIND-LEACH, AND ELECTROLYTIC DISINTEGRATION. |
1 |
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E 1.99:in-1019
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SLOW NEUTRON SCATTERING KERNELS FOR H₂O AT 423 DEG K AND 550 DEG K |
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E 1.99:in-1020
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MODEL FOR CALCULATING THE SLOW NEUTRON SCATTERING BY LIQUID D₂O |
1 |
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E 1.99:in--1021
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NEUTRON RESONANCE ABSORPTION. |
1 |
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E 1.99:in--1022
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THE TRA SAFEGUARD COMMITTEE. |
1 |
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E 1.99:in--1024
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NEUTRON ACTIVATION CROSS SECTIONS FOR THE ⁶°Co ISOMERS. |
1 |
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E 1.99:in--1025
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LINEAR-MOTION BENT-CRYSTAL GAMMA-RAY SPECTROMETER. |
1 |
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E 1.99:in--1026
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NEUTRON TOTAL AND ABSORPTION CROSS SECTIONS OF ²³⁸Pu. |
1 |
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E 1.99:in--1027
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STEADY STATE HEAT CONDUCTION WITH IRREGULAR SHAPED BOUNDARIES. |
1 |
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E 1.99:in--1032
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MATHEMATICAL AND EXPERIMENTAL ANALYSIS OF HEAT DISSIPATION FROM CYLINDRICAL SOURCES BURIED IN SOIL. |
1 |
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E 1.99:in--1033
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VARIATION WITH NEUTRON ENERGY OF THE YIELD OF HIGH KINETIC ENERGY FRAGMENTS FROM ²³³U, ²³⁵U, AND ²³⁹Pu. |
1 |
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E 1.99:in--1040
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TABULATION OF THE ²²⁸Th TOTAL NEUTRON CROSS SECTIONS FOR THE 1.9 AND 7.5 eV RESONANCES. |
1 |
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E 1.99:in--1043
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STATUS REPORT ON ADVANCED TEST REACTOR BERYLLIUM SURVEILLANCE PROGRAM. |
1 |
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E 1.99:in--1045
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MULTIPLE SCATTERING OF THERMAL NEUTRONS. |
1 |
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E 1.99:in--1047
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CALCULATING REACTOR POWER FROM ACTIVATION TECHNIQUES AS APPLIED TO AN UNUSUAL FUEL GEOMETRY (ATRC). |
1 |
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E 1.99:in--1048
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NUCLEAR TECHNOLOGY BRANCHES QUARTERLY REPORT, JULY 1--SEPTEMBER 30, 1966. |
1 |
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E 1.99:in--1052
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AXIAL FATIGUE OF PRE- AND POST-IRRADIATED A 302 B AND A 212 B STEELS. |
1 |
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E 1.99:in--1053
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A SUMMARY OF DATA FROM THE ATRC EXPERIMENTAL PROGRAM. |
1 |
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E 1.99:in--1054
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THE USE OF PROTON-RECOIL SPECTROMETER WITH PULSE SHAPE DISCRIMINATION FOR SPECTRUM MEASUREMENTS IN WATER MODERATED REACTORS. |
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