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Human Factors, Instrumentation & Controls
Improving task performance, system reliability, system and personnel safety, efficiency, and effectiveness are the division's main objectives. Its major areas of interest include task design, procedures, training, instrument and control layout and placement, stress control, anthropometrics, psychological input, and motivation.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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Proving DRACO will deliver
The United States is now closer than it has been in over five decades to launching the first nuclear thermal rocket into space, thanks to DRACO—the Demonstration Rocket for Agile Cislunar Orbit.
J.M. Perlado, J. Sanz,a D. Guerra, A.S. Perez
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 709-715
Inertial Fusion | doi.org/10.13182/FST91-A29428
Articles are hosted by Taylor and Francis Online.
The feasibility of the ferritic alloy HT-9 as the main component of the first structural wall (FSW) of inertial confinement fusion (ICF) reactors, such as HIBALL-II or LIBRA, which use thin film liquid protection through porous tubes (INPORT) has been studied in terms of radiation damage and activation. Swelling and shift in the ductile brittle transition temperature (DBTT) have been analyzed in the light of the results of experimental fast breeder reactors, which are demonstrated to be good experimental tools in our ICF range. The good performance of HT-9 is remarkable. An analysis of the generation of new solid transmutants and the depletion of initial constituents is given. Activation has been studied using recycling and shallow land burial (SLB) criteria. The interest has been focussed in a reduced activation HT-9 (Niobium-free). Recycling using HT-9 is shown to be not feasible. SLB waste disposal is also not feasible. The critical role of some short lived isotopes as Pt193, Nb93m, Re186 is analyzed, together with that of the more conventional Re186m, Nb94, Bi210m.