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Ion irradiation induced nucleation and growth of nanoparticles in amorphous silicon carbide at elevated temperatures
10.1016/j.jnucmat.2018.04.005 2018-04-04 Ion irradiation induced crystallization in as-deposited amorphous SiC films is investigated using grazing-angle incidence x-ray diffraction (GIXRD), transmission electron microscopy (TEM) and Raman spectroscopy. Irradiation with 5 MeV Xe to fluence of 1.15 × ... |
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Metallurgical characterization of melt-spun ribbons of U-5.4 wt%Nb alloy
10.1016/j.jnucmat.2018.02.002 2018-04-04 The microstructures and micro-mechanical properties of the melt-spun ribbons of U-5.4 wt%Nb alloy were characterized using optical microscopy, scanning electron microscopy, X-ray diffraction and nanoindentation. Observed variations in microstructures and prop... |
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Experimental studies on eutectic formation between metallic fuel and HT-9M cladding in a single-pin core structure of a sodium-cooled fast reactor
10.1016/j.jnucmat.2018.04.003 2018-04-03 Metallic fuel relocation experiments were conducted in which molten uranium was dropped into the cladding of a single fuel pin where eutectic interaction between fuel and cladding led to the release of eutectic fuel mixture into a narrow sodium channel. The t... |
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Correction to APT chemical composition measurements in ODS steels nano-particles
10.1016/j.jnucmat.2018.03.057 2018-04-03 Experimental artefacts occur during atom probe tomography (APT) analysis of oxide dispersion strengthened (ODS) steel particles. They skew the chemical composition measurements and the observed morphology of the particles. This study is mainly focused on chem... |
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Young's modulus evaluation of high burnup structure in UO2 with nanometer resolution
10.1016/j.jnucmat.2018.04.004 2018-04-03 The mechanical properties of a well-characterized irradiated light water reactor fuel pin with an average burnup of 72 MWd/kgU were investigated by utilizing nano-indentation technique. Young's modulus and hardness are reported as functions of radial position... |
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Immobilization of iodine via copper iodide
10.1016/j.jnucmat.2018.04.002 2018-04-03 CuI is a candidate wasteform for the immobilization of the fission product 129I. CuI can be made simply by the addition of CuCl to an I− bearing solution such that exchange of Cl− with I− takes place. The CuI material can then be consolidated into a wasteform... |
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Dissolution behavior of MgO based inert matrix fuel for the transmutation of minor actinides
10.1016/j.jnucmat.2018.04.001 2018-04-03 This study explores the dissolution properties of magnesia-based inert matrix nuclear fuel (IMF) containing transuranium elements (TRU). Pure MgO pellets as well as MgO pellets containing CeO2, as surrogate for TRU oxides, and are considered as model systems ... |
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First-principles study of solvent-solute mixed dumbbells in body-centered-cubic tungsten crystals
10.1016/j.jnucmat.2018.03.052 2018-04-03 Tungsten (W) is considered as a promising candidate for plasma-facing materials for future nuclear fusion devices, and selecting optimal alloying constituents is a critical issue to improve radiation resistance of the W alloys as well as to improve their mech... |
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Low cycle fatigue and creep fatigue interaction behavior of 9Cr-0.5Mo-1.8W-V-Nb heat-resistant steel at high temperature
10.1016/j.jnucmat.2018.03.055 2018-04-03 In this paper, Low Cycle Fatigue (LCF) and Creep-Fatigue Interaction (CFI) behavior of 9Cr-0.5Mo-1.8 W-V-Nb heat-resistant steel (ASME Grade P92 steel) at elevated temperature of 600 °C are investigated. Strain controlled LCF tests are conducted in fully reve... |
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A modified correlation between KJIC and Charpy V-notch impact energy of Chinese SA508-III steel at the upper shelf
10.1016/j.jnucmat.2018.03.056 2018-04-03 The fracture toughness plays a significant role in the structural integrity assessment of reactor pressure vessels (RPVs) in service temperature. The Charpy V-notch (CVN) impact test is used to estimate fracture toughness (KIC or KJIC) indirectly since univer... |