E 1.99:anl-ifr--90
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Analysis of fission-gas behavior with the STARS code Steady-state irradiation of U-Pu-Zr fuel pins. |
1 |
E 1.99:anl-ifr--91
|
Reactor material debris formation scoping tests |
1 |
E 1.99:anl-ifr--93
|
Calculation of the liquidus and solidus in the plutonium-uranium-zirconium system |
1 |
E 1.99:anl-ifr--94
|
Thermal conductivity of 304 stainless steel and U-11.4 wt {percent} Zr alloy between 600 and 1200 K |
1 |
E 1.99:anl-ifr--102
|
Metallic fuel safety assessment |
1 |
E 1.99:anl-ifr--103
|
A program to resolve the safety implications of fuel damage in the operation of advanced metal-fueled reactors |
1 |
E 1.99:anl-ifr--104
|
Compatibility of low-burnup U-1OZr fuel with HT9 cladding at elevated temperatures |
1 |
E 1.99:anl-ifr--109
|
Compatibility of U-Pu-Zr alloy fuel with stainless steel cladding |
1 |
E 1.99:anl-ifr--110
|
Prediction of temperature in an uncooled EBR-II subassembly heated by fission product decay |
1 |
E 1.99:anl-ifr--112
|
Fuel motion in TREAT tests M5F1, M5F2, M6 and M7 preliminary analysis of hodoscope data. |
1 |
E 1.99:anl-ifr-112
|
Fuel Motion in TREAT Tests M5F1, M5F2, M6, and M7 Preliminary Analysis of Hodoscope Data. |
1 |
E 1.99:anl-ifr--118
|
SASSYS Analysis of Fission Gas Release from High-Burnup Subassemblies in EBR-II |
1 |
E 1.99:anl-ifr--124
|
First overpower tests of metallic IFR [Integral Fast Reactor] fuel in TREAT [Transient Reactor Test Facility] Data and analysis from tests M5, M6, and M7. |
1 |
E 1.99:anl-ifr-131
|
Sodium bond defect investigations |
1 |
E 1.99:anl-ifr--152
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Fuel/cladding compatibility in low-burnup U-26Pu-10Zr/HT9 fuel at elevated temperatures |
1 |
E 1.99:anl-ifr--153
|
Validation of the REBUS-3/RCT methodologies for EBR-II core-follow analysis |
1 |
E 1.99:anl-ifr--155
|
Integral Fast Reactor Program quarterly progress report, July--September 1991 |
1 |
E 1.99:anl-ifr-156
|
Experimental and analytical studies of passive heat removal systems for advanced LMRs. |
1 |
E 1.99:anl-ifr--169
|
Integral Fast Reactor Program annual progress report, FY 1991 |
1 |
E 1.99:anl-ifr-169
|
Integral Fast Reactor Program annual progress report, FY 1991 |
1 |