E 1.99:ucid-19667
|
Single-station locations of seismic events |
1 |
E 1.99:ucid-19668
|
High-current beam transport in the FXR injector |
1 |
E 1.99:ucid--19672
|
Drilling-induced borehole-wall damage at spent fuel test-climax |
1 |
E 1.99:ucid-19673
|
Four-way rf beam separator |
1 |
E 1.99:ucid-19674
|
Calculation of a tracking force |
1 |
E 1.99:ucid-19675
|
Influence of centering forces on IFR hose instability |
1 |
E 1.99:ucid-19676
|
Calculation and interpretation of In-Situ measurements of initial radiations at Hiroshima and Nagasaki |
1 |
E 1.99:ucid-19689
|
Mechanical properties of vapor-deposited thin metallic films a status report. |
1 |
E 1.99:ucid-19690
|
DMSP/MFR total ozone and radiance data base |
1 |
E 1.99:ucid-19692
|
Review of intense-ion-beam propagation with a view toward measuring ion energy |
1 |
E 1.99:ucid-19696
|
Microwave energy storage in resonant cavities |
1 |
E 1.99:ucid-19700
|
Human-factors engineering control-room design review/audit Waterford 3 SES Generating Station, Louisiana Power and Light Company. |
1 |
E 1.99:ucid-19701
|
Technical issues related to NUREG 0800, Chapter 18 Human Factors Engineering/Standard Review Plan. |
1 |
E 1.99:ucid-19702
|
Tables of cross references among SECY 82-111, NUREG 0700, NUREG 0835, NUREG 0801 |
1 |
E 1.99:ucid-19707
|
Preliminary systems-interaction results from the Digraph Matrix Analysis of the Watts Bar Nuclear Power Plant safety-injection systems |
1 |
E 1.99: ucid-19719
|
Seismic Safety Margins Research Programs. Assessment of potential increases in risk due to degradation of steam generator and reactor coolant pump supports. [PWR] |
1 |
E 1.99:UCID-19722
|
Reliability analysis of stiff versus flexible piping. Status report |
1 |
E 1.99:ucid-19725
|
Impact of inservice inspection on the reliability of nuclear piping |
1 |
E 1.99:ucid-19729
|
Leaching study of nuclear melt glass Part I. |
1 |
E 1.99:ucid-19730
|
Fusion-neutron effects on magnetoresistivity of copper stabilizer materials |
1 |