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E 1.99:anl-wis-pa-000001, rev 02/acn 01
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EBS Radionuclide Transport Abstraction |
1 |
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E 1.99:anl-wis-pa-000002 rev 03
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ENGINEERED BARRIER SYSTEM FEATURES, EVENTS, AND PROCESSES |
1 |
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E 1.99:anl-wis-pa-000002, rev 05
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ENGINEERED BARRIER SYSTEM FEATURES, EVENTS, AND PROCESSES |
1 |
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E 1.99:anl-wis-pa-000002, rev 05 acn 01
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ENGINEERED BARRIER SYSTEM FEATURES, EVENTS AND PROCESSES |
1 |
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E 1.99: anl-wis-pa-000003,rev 00, dc # 23390
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Performance Assessment and Sensitivity Analyses of Disposal of Plutonium as Can-in-Canister Ceramic, Rev. 00 |
1 |
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E 1.99:anl-wis-pa-000004 rev 00
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USE OF ONE-ON ANALYSIS TO EVALUATE TOTAL SYSTEM PERFORMANCE |
1 |
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E 1.99: anl-wm
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DISSOCIATION PRESSURES OF URANIUM HYDRIDE AND URANIUM TRITIDE |
1 |
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E 1.99: anl-wmm-9
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ABSORPTION SPECTRA OF LANTHANIDE AND ACTINIDE RARE EARTHS. II. TRANSITION PROBABILITIES FOR +3 IONS IN THE TWO SERIES |
1 |
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E 1.99: anl-wmm-341
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The Potentials of the Uranium Three-Four and Five-Six Couples in Perchloric and Hydrochloric Acids |
1 |
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E 1.99: anl-wmm-759
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DISSOCIATION PRESSURES OF URANIUM HYDRIDE AND URANIUM TRITIDE |
1 |
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E 1.99:anl-wmm-1041
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Solvent extraction properties of monooctyl phosphate and dioctyl phosphate on elements of interest to the Atomic Energy Commission |
1 |
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E 1.99:anl-wmm-1156
|
THE HALF LIFE OF U$sup 23$$sup 2$ |
1 |
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E 1.99:anl-wpb--45
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Heat Transfer Consideration in Reactor Design Part 1. |
1 |
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E 1.99:anl-wpb--73
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Reactor Hazards Meeting. |
1 |
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E 1.99:anl-wpb--79
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Two types of exponential experiments for D2O Piles. |
1 |
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E 1.99:anl-wpb--80
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Tentative set of constants for natural Uranium Reactors. |
1 |
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E 1.99:anl-wpb--96
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Neutron and Heat distribution with Four-Clumped Rods. |
1 |
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E 1.99:anl-wpb--108
|
Test Pile |
1 |
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E 1.99:anl-wpb--124
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Modified CP-5 Reactor for Polonium production summary. |
1 |
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E 1.99:anl-wpb--135
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Review of Aluminum Water Reactor. |
1 |
