E 1.99:hdc--2457
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RDA DC-6 -- Design criteria for reactor water plant at Coyote Rapids site. Instruction letter number 1 |
1 |
E 1.99:hdc--2462
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Safety control system for RDA-DC3 |
1 |
E 1.99:hdc--2466
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Interim report RDA-DC-3 and Program X |
1 |
E 1.99:hdc--2467
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Proposed water plant expansion (C-482) |
1 |
E 1.99:hdc--2490
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Minimum pressure requirements at top of riser -- RDA DC-6, cooling water studies |
1 |
E 1.99:hdc--2499
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Safety system for RDA-DC-3 |
1 |
E 1.99:hdc--2513
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Permissible design pressures for 2S-H14-72S clad process tubes |
1 |
E 1.99:hdc--2523
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Water requirements at 105-K immediately following an electrical outage |
1 |
E 1.99:hdc--2524
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Basic design specification for ̀̀X̀̀ Pile |
1 |
E 1.99:hdc--2529
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Review and recommendations concerning the location of proposed additional separation plant East versus West Areas |
1 |
E 1.99:hdc--2530
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Design basis for proposed separations facility, for use in preliminary project proposal |
1 |
E 1.99:hdc--2534
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300 Area ̀̀X̀̀ Program, Basis ̀̀B̀̀ |
1 |
E 1.99:hdc--2553-fd
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Final draft for Program X descriptive criteria, architectural and structural |
1 |
E 1.99:hdc--2557
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RDA-DC-3 and Program X, process tube assembly -- Design criteria (preliminary) |
1 |
E 1.99:hdc--2560
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Design criteria for the biological shield |
1 |
E 1.99:hdpo/04-13
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ES-3100 A New Generation Shipping Container for Bulk Highly Enriched Uranium and Other Fissile Materials. |
1 |
E 1.99:hdr-89-aop-4
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Hot dry rock geothermal energy development program Annual operating plan, fiscal year 1989. |
1 |
E 1.99:hdtada
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HDTADA |
1 |
E 1.99: he-2-5
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Some Trends in High-Energy Proton-Nucleus Interactions in Nuclear Emulsion. |
1 |
E 1.99:he-150-189
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TRANSIENT TEMPERATURE DISTRIBUTIONS IN A THERMALLY ORTHOTROPIC PLATE WITH NON-UNIFORM SURFACE HEATING (thesis) |
1 |