E 1.99:etec-tdr-82-2
|
Snubber qualification and test requirements |
1 |
E 1.99:etec-tdr-84-6
|
Containment purge and vent valve program. Final report |
1 |
E 1.99:etec-tdr-85-5
|
Molten salt freeze seal. Final report |
1 |
E 1.99: etf-760.92-2/4
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DEVELOPMENT OF A RADIOACTIVE-DUST COLLECTOR. PROGRESS REPORT NO. 4 |
1 |
E 1.99:eto-08-0029
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U. S. Department of Energy Air Emissions Annual Report 40 Code of Federal Regulations (CFR) 61.94, Subpart H Calendar Year 2007 - DE-AC05-98OR22700 Calendar Year 2007 Oak Ridge Reservation Air Emissions Annual Report Certification. |
1 |
E 1.99:etp-discussionpaper-2008-21
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Technology and international climate policy |
1 |
E 1.99:etp-discussionpaper-2009-04
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Proposed roadmap for overcoming legal and financial obstacles to carbon capture and sequestration |
1 |
E 1.99:etp-discussionpaper-2009-05
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In-use vehicle emissions in China Beijing study. |
1 |
E 1.99:etp-discussionpaper-2009-07
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Biofuels and certification. A workshop at the Harvard Kennedy School of Government. Summary report |
1 |
E 1.99:etp-discussionpaper-2009-08
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Realistic costs of carbon capture |
1 |
E 1.99: etr-120
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STUDY OF THE KINETICS OF LOADING Pu(IV) ON PERMUTIT SK RESIN FROM 7.2 M NITRIC ACID |
1 |
E 1.99: etr-123
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WASHING BEHAVIOR OF Pu(IV) CHARGE ON A PERMUTIT SK, 40-73 MESH COLUMN |
1 |
E 1.99: etr-125
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I. STUDY OF THE KINETICS OF Pu(IV) ELUTION FROM PERMUTIT SK RESIN, 40-70 MESH, AT 60 BY 0.6 M NITRIC ACID. II. STUDY OF RESIN REGENERATION BY 7.2 M NITRIC ACID. III. CALCULATION FOR A PLUTONIUM PURIFICATION COLUMN OF 40-70 MESH PERMUTIT SK |
1 |
E 1.99: etr--181
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STUDY OF URANIUM(IV) NITRATE AS REDUCING AGENT FOR PLUTONIUM. IIa. STABILITY OF URANIUM(IV) IN SOLUTION. |
1 |
E 1.99: etr--210
|
Aqueous reprocessing in a multi-purpose plant |
1 |
E 1.99: etr--220
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The determination of nitrous acid in Purex process solutions. 1. Direct spectrophotometric determination of nitrous acid dissolved in tributyl phosphate phases |
1 |
E 1.99: eur
|
PROCEEDINGS OF THE USAEC SYMPOSIUM ON ZIRCONIUM ALLOY DEVELOPMENT, HELD IN CASTLEWOOD, PLEASANTON, CALIFORNIA, NOVEMBER 12-14, 1962 |
1 |
E 1.99:eur--85.e
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ORGEL a European power reactor design. |
1 |
E 1.99: eur--333.i
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Liquid scintillator tritium determination in the urines of staff members of a nuclear center; Determinazione del Tritio con Scintillatore Liquido Nelle Urine del Personale di un Centro Nucleare |
1 |
E 1.99: eur--1585en-vol.1
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Probabilistic accident consequence uncertainty analysis Dispersion and deposition uncertainty assessment, main report. |
1 |