E 1.99: conf-830901-13
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TRAC calculations of overcooling transients in PWRs for pressurized thermal-shock analysis |
1 |
E 1.99: conf-830901-14
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TRAC-PF1 analysis of LOFT steam-generator feedwater transient test L9-1. [PWR] |
1 |
E 1.99: conf-830901-15
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TRAC-PF1 pressurized-thermal shock calculations for several small-break loss-of-coolant accident transients in the Oconee-1 nuclear power plant. |
1 |
E 1.99: conf-830901-16
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TRAC-PF1 post-test predictions for the Semiscale Natural-Circulation Tests S-NC-2 and S-NC-6. [PWR] |
1 |
E 1.99: conf-830901-17
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Small-break LOCA recovery in B and W plants. [PWR] |
1 |
E 1.99: conf-830901-20
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Transients - abnormal and otherwise |
1 |
E 1.99: conf-830901-22
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Boron injection at natural circulation conditions in PWRs |
1 |
E 1.99: conf-830901-23
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Control rod trip failures. Salem 1 the cause, response and potential fixes. |
1 |
E 1.99:conf-830905-1
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85,000-GPM, single-stage, single-suction LMFBR intermediate centrifugal pump |
1 |
E 1.99: conf-830905-3
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Comparison of calculated results from two analytical models with measured data from a heat-exchanger flow test |
1 |
E 1.99:conf-830905-5
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CRBR pump water test experience |
1 |
E 1.99: conf-830905-8
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Transportation research activities in support of nuclear waste management programs |
1 |
E 1.99:conf-830905-9
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CRBRP steam-generator design evolution |
1 |
E 1.99:conf-830905-12
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Operating experience of the EBR-II intermediate heat exchanger and the steam generator system |
1 |
E 1.99: conf-830908-1
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Recent results from the ZT-40M reversed-field pinch program |
1 |
E 1.99: conf-830908-2
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Recent results in the Los Alamos compact torus program |
1 |
E 1.99: conf-830908-5
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Status of tandem-mirror confinement |
1 |
E 1.99:conf-830908-7
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Neutral injection experiments on the ISX-B tokamak |
1 |
E 1.99:conf-830908-8
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ATF-1 torsatron studies |
1 |
E 1.99: conf-830909-1
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Magnetic-mirror principle as applied to fusion research |
1 |