E 1.99: conf-911074--1
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A re-evaluation of the Moyuta geothermal system, Southern Guatemala |
1 |
E 1.99: conf-911074--2
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Imaging of reservoirs and fracture systems using microearthquakes induced by hydraulic injections |
1 |
E 1.99: conf-911074--3
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Alternate operating strategies for Hot Dry Rock geothermal reservoirs |
1 |
E 1.99: conf-911079--
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Transactions of the nineteenth water reactor safety information meeting |
1 |
E 1.99:conf-911079-1
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BWR lower plenum debris bed models for MELCOR |
1 |
E 1.99:conf-911079-2
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Assessment of two BWR accident management strategies |
1 |
E 1.99:conf-911079-3
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Aging assessment of BWR control rod drive systems |
1 |
E 1.99: conf-911079--4
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Snubber aging assessment Results of NPAR Phase 2 in-plant research. |
1 |
E 1.99:conf-911079-5
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Iodine chemical forms in LWR severe accidents |
1 |
E 1.99:conf-911079-7
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Heavy-Section Steel Technology Program Recent developments in crack initiation and arrest research. |
1 |
E 1.99: conf-911079--8
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Progress in evaluation and improvement in nondestructive examination reliability for inservice inspection of Light Water Reactors (LWRs) and characterize fabrication flaws in reactor pressure vessels |
1 |
E 1.99: conf-911079--9
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Calculation of fuel pin failure timing under LOCA conditions |
1 |
E 1.99: conf-911079--13
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Analyses of corium spreading in Mark I containment geometry |
2 |
E 1.99: conf-911079--15
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An approach for assessing ALWR passive safety system reliability |
1 |
E 1.99: conf-911079--17
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Detecting and mitigating aging in component cooling water systems |
2 |
E 1.99: conf-911079--20
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Analysis of postulated events for the revised ALMR/PRISM design |
2 |
E 1.99: conf-911079--22
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High level seismic/vibrational tests at the HDR An overview. |
2 |
E 1.99: conf-911079--23
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Estimation of mechanical properties of cast stainless steels during thermal aging in LWR systems |
1 |
E 1.99: conf-911079--24
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Mechanical-property degradation of cast stainless steel components from the Shippingport reactor |
2 |
E 1.99: conf-911079--26
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Fatigue and environmentally assisted cracking in light water reactors |
2 |