E 1.99:anl/ed/cp--95702
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Deactivation of the EBR-II complex |
1 |
E 1.99:ANL/ED/CP--95703
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Applications of high resolution ICP-AES in the nuclear industry |
1 |
E 1.99:ANL/ED/CP-95726
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Impact of mental representational systems on design interface. |
1 |
E 1.99:anl/ed/cp--95729
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Pilot-scale equipment development for pyrochemical reduction of spent oxide fuel |
1 |
E 1.99:ANL/ED/CP-95878
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Equipment design guidelines for remote hot cell operations. |
1 |
E 1.99:ANL/ED/CP-96045
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Consolidation of cladding hulls from the electrometallurgical treatment of spent fuel. |
1 |
E 1.99:ANL/ED/CP-96366
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Thermal hydraulic calculations to support increase in operating power in McClellen Nuclear Radiation Center(MNRC) TRIGA reactor. |
1 |
E 1.99:ANL/ED/CP-96423
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A Versatile two-step process for immobilizing excess plutonium. |
1 |
E 1.99:ANL/ED/CP-96471
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EBR-II blanket fuel leaching test using simulated J-13 well water. |
1 |
E 1.99:ANL/ED/CP-96583
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The effect of low dose-rate irradiation on the microstructure of 304 stainless steel. |
1 |
E 1.99:ANL/ED/CP-97218
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Graphical user interfaces for McCellan Nuclear Radiation Center (MNRC). |
1 |
E 1.99:anl/ed/cp-97347
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The effect of low dose rate irradiation on the swelling of 12% cold-worked 316 stainless steel. |
1 |
E 1.99:ANL/ED/CP-97520
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US-RERTR Advanced Fuel Development Plans 1999. |
1 |
E 1.99:ANL/ED/CP-97538
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Fuel powder production from ductile uranium alloys. |
1 |
E 1.99:ANL/ED/CP-97584
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Postirradiation examination of high-density uranium alloy dispersion fuels. |
1 |
E 1.99:ANL/ED/CP-97607
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A study of thermal stratification in the cold legs during the subcooled blowdown phase of a loss of coolant accident in the OSU APEX thermal hydraulic testing facility. |
1 |
E 1.99:ANL/ED/CP-98418
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Hydrodynamic simulation of a lithium chloride salt system. |
1 |
E 1.99:ANL/ED/CP-98713
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Liquid metal reactor deactivation as applied to the experimental breeder reactor - II. |
1 |
E 1.99:ANL/ED/CP-98816
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TEM investigation of a ceramic waste form for immobilization of process salts generated during electrometallurgical treatment of spent nuclear fuel. |
1 |
E 1.99:ANL/ED/CP-99102
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Speaker recognition through NLP and CWT modeling. |
1 |