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E 1.99:anl-ifr--6
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Assessment of fission-gas-induced transient swelling in metallic fuel |
1 |
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E 1.99:anl-ifr--13
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Fuel/cladding compatibility of U-10Zr and U-5Fs fuels with advanced alloy cladding materials |
1 |
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E 1.99:anl-ifr--16
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Characteristics of high level wastes from a pyrochemical process |
1 |
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E 1.99:anl-ifr--17
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Direct electrical heating of irradiated EBR-II Mark-II driver fuel |
1 |
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E 1.99:anl-ifr--18
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IFR safety tests M2 and M3 in TREAT data and analysis. |
1 |
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E 1.99:anl-ifr--19
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Test description for the Integral Fast Reactor subassemblies X419, X420, and X421 |
1 |
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E 1.99:anl-ifr--23
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FPIN2 analysis of metal fueled pins |
1 |
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E 1.99:anl-ifr--27
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Gas-bubble growth mechanisms in the analysis of metal fuel swelling |
1 |
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E 1.99:anl-ifr--29
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Metallic fuels handbook |
1 |
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E 1.99:anl-ifr--30
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Dynamics of axial extrusion of metallic fuel during overheating transients |
1 |
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E 1.99:anl-ifr--32
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Zirconium migration in metal fuels |
1 |
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E 1.99:anl-ifr--33
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Test Design Description (TDD). Volume 1A. Design description and safety analysis for IFR-1 metal fuels irradiation test in FFTF |
1 |
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E 1.99:anl-ifr--36
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Compatibility of U-Pu-Zr fuels with advanced clad alloys onset-of-melting results. |
1 |
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E 1.99:anl-ifr--37
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Local fault tolerance of metal fuel |
1 |
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E 1.99:anl-ifr--39
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Special handling and preheating requirements for IFR-1 metal fuel experiment in FFTF |
1 |
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E 1.99:anl-ifr--42
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Final safety analysis report for the IFR Experimental Fuels Laboratory |
1 |
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E 1.99:anl-ifr--43
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Test design description. Volume 1B. IFR-1 metal fuel irradiation (AK-181) |
1 |
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E 1.99:anl-ifr--44
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Test design description Volume 2, Part 1. IFR-1 metal fuel irradiation test (AK-181) element as-built data |
1 |
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E 1.99:anl-ifr--45
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Fission gas retention and axial expansion of irradiated metallic fuel |
1 |
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E 1.99:anl-ifr--49
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Thermoelastic stresses in U-Pu-Zr ternary alloy fuels. An analytical interpretation of results in the IFR lead irradiation experiments |
1 |
