Tensile properties of reduced activation Fe-9Cr-2W steels after FFTF irradiation
Kurishita, H.; Kayano, H.; Narui, M.
German National Library of Science and Technology (GetInfo) (German)
Synergistic influence of displacement rate and helium/dpa ratio on swelling of Fe-(9, 12)Cr binary alloys in FFTF at ∼400 ^oC
Garner, F. A.; Gelles, D. S.; Greenwood, L. R.
Shear punch testing of ^5^9Ni isotopically-doped model austenitic alloys after irradiation in FFTF at different He/dpa ratios
Hankin, G. L.; Toloczko, M. B.; Hamilton, M. L.
Review of Fast Flux Test Facility (FFTF) Fuel Experiments for Storage in Interim Storage Casks (ISCs)
Thielges, J. R.; Department of Energy, Washington, DC.
Response of dynamically compacted tungsten to high fluence neutron irradiation at 423-600�C in FFTF
Megusar, J.; Garner, F. A.
Response of dynamically compacted tungsten to high fluence neutron irradiation at 423 600�C in FFTF
Reactor Component Inventory System at FFTF
Ordonez, C. R.; Redekopp, R. D.; Reed, E. A.
Radiological Considerations of the Reactor Cover Gas Processing System at the FFTF (Fast Flux Test Facility)
Prevo, P. R.; Department of Energy, Washington, DC
Overview of FFTF contributions to Liquid Metal Reactor Safety
Waltar, A. E.; Padilla, A.; Department of Energy, Washington, DC
Microstructural response of titanium-modified austenitic stainless steels to neutron exposure of 70 dpa in FFTF/MOTA
Katoh, Y.; Kohno, Y.; Kohyama, A.
Irradiation creep of various ferritic alloys irradiated at 400�C in the PFR and FFTF reactors
Toloczko, M. B.; Garner, F. A.; Eiholzer, C. R.
Irradiation creep of low-activation ferritic steels in FFTF/MOTA
Kohyama, A.; Kohno, Y.; Asakura, K.
Influence of helium generation rate and temperature history on mechanical properties of model Fe-Cr-Ni alloys irradiated in FFTF at relatively low displacement rates
Hamilton, M. L.; Garner, F. A.; Edwards, D. J.
Evaluation of selected ex-reactor accidents related to the tritium and medical isotope production mission at the FFTF
Himes, D. A.; Department of Energy, Washington, DC
Effect of FFTF irradiation on tensile properties of P- and Ti-modified model austenitic alloys with small amounts of boron
Kurishita, H.; Muroga, T.; Watanabe, H.
Dimensional stability, optical and elastic properties of MgAl~2O~4 spinel irradiated in FFTF to very high exposures
Garner, F. A.; Hollenberg, G. W.; Hobbs, F. D.
Calculated Damage Rates for FFTF Structural Components and Surveillance Assemblies
Simons, R. L.; American Society for Testing and Materials; Euratom
An Automated Tensile Machine for Small Specimens Heavily Neutron Irradiated in FFTF/MOTA
Kohyama, A.; Shato, S.; Hamada, K.
FFTF reactor immersion heaters. Revision 1
Romrell, D. M.
FFTF (Fast Flux Test Facility) Reactor Shutdown System Reliability Reevaluation
Pierce, B. F.; Department of Energy, Washington, DC
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