Andrew Worrall

TL;DR: In this article, the neutronics of alternate cladding materials in a pressurized water reactor (PWR) environment were analyzed and the associated neutronics penalty/advantage, changes in reactivity coefficients, and spectral variations once a transition in the cladding was made.

TL;DR: In this article, a Python script known as ChemTriton has been developed to simulate equilibrium MSR fuel cycle performance by modeling the changing isotopic composition of an irradiated fuel salt using SCALE for neutron transport and depletion calculations.

TL;DR: The fluoride salt-cooled high-temperature reactor (FHR) demonstration reactor (DR) as mentioned in this paper is a concept for a saltcooled reactor with 100 megawatts of thermal output, which uses tristructuralisotropic (TRISO) particle fuel in compacts within prismatic graphite blocks.

TL;DR: In this paper, the authors present analyses of possible reactor representations of a nuclear fuel cycle with continuous recycling of thorium and produced uranium (mostly U-233) with thorium-only feed.

TL;DR: In this paper, the authors analyzed the fuel cycle performance and core design of the Transatomic Power liquid-fueled molten salt reactor concept, which uses configurable zirconium hydride moderator rod assemblies to shift the neutron spectrum in the core from intermediate at beginning of life to thermal at end of life.

TL;DR: A review of the development status for three accident tolerant fuel cladding technologies, namely coated zirconium-based cladding, ferritic alumina-forming alloy cladding and silicon carbide fiber-reinforced SCCM composite, is offered in this paper.

TL;DR: In this paper, a set of model FeCrAl alloys containing 10−20Cr, 3−5Al, and 0−0.12Y in weight percent, were prepared by conventional arc-melting and hot-working processes to explore the effect of composition on the properties of FecrAlY alloys.

TL;DR: In this paper, the impact of alloying elements on the material properties of Zirconium-based claddings has been systematically presented, including the impact on coating layer on the surface of Zr-based alloys, mainly referring coating materials and fabrication methods.

TL;DR: In this paper, a series of Fe-Cr-Al alloys with 10 −18 ¼ % Cr and 2.9 −4.9 % Al were irradiated at 382 −C to 1.8 dpa to investigate the irradiation-induced microstructural and mechanical property evolution as a function of alloy composition.