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A Mathematical Model Design for Pu Content Analyzed by 244Cm in Spent Fuel of Fast Reactors
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: Pyroprocessing is employed in the reprocessing of integral fast reactors (IFRs). According to China's domestic regulations of nuclear material control, analysis of the content of uranium (U) and plutonium (Pu) should be ...
K-Edge Measurement Technology Simulation Model Design
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: The K-edge technique is a nondestructive analysis (NDA) method that provides key data for nuclear material accountancy, mainly for the measurement of U and Pu concentrations in spent fuel reprocessing processes, with an ...
Spatial Distribution Assay of Active Neutron Counting
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: In response to the nuclear material accounting and control system, uranium or plutonium mass and also the isotope abundance should be quantified comprehensively. Commonly, in nuclear safeguards and nuclear security field, ...