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E 1.99:ga--10001
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EFFECT OF TEMPERATURE HISTORY ON THE DIMENSIONAL CHANGES OF NUCLEAR GRAPHITES. |
1 |
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E 1.99:ga--10010
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PUBLIC SERVICE COMPANY OF COLORADO 330-MW(e) HIGH-TEMPERATURE GAS-COOLED REACTOR RESEARCH AND DEVELOPMENT PROGRAM. Quarterly Progress Report for the Period Ending March 31, 1970. |
1 |
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E 1.99:ga--10073
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FISSION PRODUCT TRANSPORT IN HTGR SYSTEMS A SUMMARY. |
1 |
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E 1.99:ga--10088
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HTGR BASE PROGRAM QUARTERLY PROGRESS REPORT FOR THE PERIOD ENDING MAY 31, 1970. |
1 |
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E 1.99:ga--10099
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40-MW(E) PROTOTYPE HIGH-TEMPERATURE GAS-COOLED REACTOR POSTCONSTRUCTION RESEARCH AND DEVELOPMENT PROGRAM. Quarterly Progress Report for the Period Ending April 30, 1970. |
1 |
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E 1.99:ga--10146
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FAST REACTOR SPECTRUM MEASUREMENTS. Quarterly Progress Report for the Period Ending April 30, 1970. |
1 |
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E 1.99: ga--10171
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STATUS REPORT ON FAST BREEDER REACTORS (WHY BREEDERS). |
1 |
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E 1.99:ga--10196
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EXAMINATION OF PEACH BOTTOM HTGR CONTROL ROD, CONTROL ROD GUIDE TUBE, AND THERMALLY RELEASED SHUTDOWN ROD CO8-01 AFTER 300 EFFECTIVE FULL POWER DAYS OF OPERATION. |
1 |
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E 1.99:ga--10200
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BUTTONHEAD ANCHORAGE OF TENDON WIRE FOR THE FORT ST. VRAIN PRESTRESSED CONCRETE REACTOR VESSEL. |
1 |
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E 1.99:ga--10202
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PUBLIC SERVICE COMPANY OF COLORADO 330-MW(e) HIGH-TEMPERATURE GAS-COOLED REACTOR RESEARCH AND DEVELOPMENT PROGRAM. Quarterly Progress Report for the Period Ending June 30, 1970. |
1 |
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E 1.99:ga--10264
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HIGH-TEMPERATURE FAST-FLUX IRRADIATION EXPERIMENT FOR MIXED-OXIDE FUEL RODS. |
1 |
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E 1.99:ga--10265
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SPECIAL DEVELOPMENT PROBLEMS OF HIGH-TEMPERATURE GAS-COOLED REACTOR SYSTEMS. |
1 |
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E 1.99:ga--10268
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RESEARCH ON GRAPHITE. Quarterly Progress Report for the Period Ending August 14, 1970. |
1 |
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E 1.99:ga--10278
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CONTROLLED THERMONUCLEAR RESEARCH PROGRAM. Summary Progress Report, August 1, 1969--July 31, 1970. |
1 |
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E 1.99:ga--10280
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FAST REACTOR SPECTRUM MEASUREMENTS. Quarterly Progress Report for the Period Ending July 31, 1970. |
1 |
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E 1.99:ga--10288
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HTGR BASE PROGRAM. Quarterly Progress Report for the Period Ending August 31, 1970. |
1 |
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E 1.99:ga-10298(amend.9)
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Gas-Cooled Fast Breeder Reactor preliminary safety information document, Amendment 9. GCFR fuel cladding PC-5 (faulted) temperature limit |
1 |
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E 1.99:ga-10298(amend.10)
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Gas-Cooled Fast Breeder Reactor Preliminary Safety Information Document, Amendment 10. GCFR residual heat removal system criteria, design, and performance |
1 |
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E 1.99:ga--10300
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40-MW(e) PROTOTYPE HIGH-TEMPERATURE GAS-COOLED REACTOR POSTCONSTRUCTION RESEARCH AND DEVELOPMENT PROGRAM. Quarterly Progress Report for the Period Ending July 31, 1970. |
1 |
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E 1.99:ga--10338
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STEAM GENERATORS FOR HIGH-TEMPERATURE GAS-COOLED REACTOR PLANTS IN THE U.S.A. |
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