2021
DOI: 10.1007/s11837-021-04873-x
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Review and Preliminary Investigation into Fuel Loss from Cermets Composed of Uranium Nitride and a Molybdenum-Tungsten Alloy for Nuclear Thermal Propulsion Using Mesoscale Simulations

Abstract: A ceramic-metal composite (cermet) of uranium nitride (UN) particles embedded in a tungsten-molybdenum (W/Mo) alloy matrix is being considered as reactor fuel for nuclear thermal propulsion (NTP). One possible issue is the loss of fissile uranium atoms during reactor operation. We begin by reviewing historical data that suggest that a likely mechanism for fuel loss is transport of free uranium along metal grain boundaries and through cracks to free surfaces. We then employ simple two-dimensional (2D) mesoscale… Show more

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Cited by 9 publications
(2 citation statements)
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“…The BISON fuel performance code provides a variety of material models for nuclear materials [61]. BISON offers material properties for W and Mo-30W CERMETs [62].…”
Section: Heat Conduction and Conjugate Heat Transfermentioning
confidence: 99%
“…The BISON fuel performance code provides a variety of material models for nuclear materials [61]. BISON offers material properties for W and Mo-30W CERMETs [62].…”
Section: Heat Conduction and Conjugate Heat Transfermentioning
confidence: 99%
“…Nevertheless, such traditional contact methods are hardly applied to various refractory metals, due to high chemical reactivity and the thermal expansion of a test apparatus at extremely high temperatures. Refractory metals are strongly preferred for applications under high temperatures (>2000 K) including materials for nuclear fusion reactors [11], hypersonic aircraft [12], and nuclear or thermal propulsion for spacecraft [13]. However, the choice of their manufacturing processes is limited due to their high level of hardness.…”
Section: Introductionmentioning
confidence: 99%