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E 1.99:ORNL/M--3738
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Detailed flux calculations for the conceptual design of the Advanced Neutron Source Reactor |
1 |
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E 1.99:ornl/m--3739
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SAS2H input for computing core activities of 4.5, 5.0, and 5.5 weight % ²³⁵U fuel for Sequoyah Nuclear Plant |
1 |
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E 1.99:ornl/m--3754
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Environmental Guidance Program reference book Toxic substances control act. Revision 7. |
1 |
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E 1.99:ornl/m--3763
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Ecological risks of DOÈs programmatic environmental restoration alternatives |
1 |
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E 1.99:ornl/m--3768
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Interim report on the post irradiation examination of capsules 2 and 3 of the HFR-B1 experiment |
1 |
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E 1.99:ornl/m--3774
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Assessment of the roles of the Advanced Neutron Source Operators |
1 |
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E 1.99: ornl/m--3778
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Technical area status report for second-stage destruction and offgas treatment |
1 |
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E 1.99:ORNL/M--3788
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Active Sites Environmental Monitoring Program FY 1994 annual report |
1 |
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E 1.99:ornl/m--3789
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FY 1993 progress report on the ANS thermal-hydraulic test loop operation and results |
1 |
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E 1.99: ornl/m--3805
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Design assessment for Melton Valley liquid low-level waste collection and transfer system upgrade project at Oak Ridge National Laboratory, Oak Ridge, Tennessee |
1 |
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E 1.99: ornl/m--3964
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Design demonstrations for category B tank systems at Oak Ridge National Laboratory, Oak Ridge, Tennessee |
1 |
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E 1.99:ornl/m--3972
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National Environmental Policy Act compliance guide. Volume II (reference book) |
1 |
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E 1.99:ornl/m-3976
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Interlaboratory comparison on estimating the long-term thermal resistance of unfaced, rigid, closed-cell, polyisocyanurate (PIR) foam insulation ? a cooperative industry/government project |
1 |
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E 1.99:ornl/m--3986
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MPI implementation of CFD program PHOENICS |
1 |
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E 1.99:ornl/m--3993
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Detailed heat load calculations at the beginning, middle, and end of cycle for the conceptual design of the Advanced Neutron Source Reactor |
1 |
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E 1.99:ornl/m--4021
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Solid state sintering of silicon nitride ARL-CR-114. Final report |
1 |
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E 1.99: ornl/m--4039
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Tritium tracer movement as an analogy for pump and treat remediation |
1 |
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E 1.99: ornl/m--4068
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Integrated Data Base report--1993 U.S. spent nuclear fuel and radioactive waste inventories, projections, and characteristics. Revision 10. |
1 |
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E 1.99:ORNL/M--4075
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Summary of corrosion loop test results for the Institut Laue-Langevin cladding material |
1 |
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E 1.99:ornl/m--4079
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Development of microwave processing of silicon nitride components for advanced heat engine applications -- Microwave annealing of silicon nitride with high additive contents. CRADA final report for CRADA Number ORNL90-0035 |
1 |
