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Input nuclear material accountancy is crucial for a pyroprocessing facility safeguards. Until a direct Pu measurement technique is established, an indirect method based on code calculations with burnup measurement and neutron counting for <sup>244</sup>Cm could be a practical option. Burnup can be determined by destructive analysis (DA) for final(More)
Background The failure modes, time to development, and clinical relevance are known to differ between proximal junctional kyphosis (PJK) and proximal junctional failure (PJF). However, there are no reports that study the risk factors of PJK and PJF separately. Objective The aim of this study was to investigate the risk factors for PJK and PJF separately.(More)
BACKGROUND AND PURPOSE Stents have been reported as an option for improvement of the recanalization rate in AIS. The authors have also used intracranial stents in failed cases of IAT with pharmacologic and mechanical methods since 2004. We retrospectively reviewed our cases of intracranial stent use for IAT of AIS for recanalization and as a rescue(More)
Radiation detectors based on semiconductors like Silicon Carbide (SiC), Aluminum Nitride (AlN), Boron Nitride (BN) and Gallium Arsenide (GaAs) with a large energy band gap are the most promising ionizing radiation detectors for high temperature and in harsh radiation fields. The present work focused on the development of a radiation resistive neutron(More)
This meta-analysis was designed to compare the effectiveness and safety of intravenous (IV) versus topical administration of tranexamic acid (TXA) in patients undergoing primary total knee arthroplasty (TKA) by evaluating the need for allogenic blood transfusion, incidence of postoperative complications, volume of postoperative blood loss, and change in(More)
Radiation dose can be determined with the radiation dosimeter. Recently, hand-held radioisotope identifier is being developed by many researchers to measure the radiation dose and to determine the type of the radioisotope. New design concept of the radioisotope identifier is introduced in this work. In this design, one can measure the radiation dose and the(More)
Prototype safeguards instrument for nuclear material accountancy (NMA) of uranium/transuranic (U/TRU) products that could be produced in a future advanced PWR fuel processing facility has been developed and characterized. This is a new, hybrid neutron measurement system based on fast neutron energy multiplication (FNEM) and passive neutron albedo reactivity(More)
An SPND (Self-powered Neutron Detector) is commonly used for neutron detection in NPP (Nuclear Power Plant) by virtue of un-reactivity for gamma-rays. But it has a drawback, which is that it cannot detect neutrons in real time due to beta emissions (about > 48 s) after reactions between neutrons and Rh in an SPND. And Generation IV reactors such as MSR(More)
The PRIDE (PyRoprocessing Integrated inactive DEmonstration) is an engineering-scale pyroprocessing test-bed facility that utilizes depleted uranium (DU) instead of spent fuel as a process material. As part of the ongoing effort to enhance pyroprocessing safeguardability, UNDA (Unified Non-Destructive Assay), a system integrating three different(More)
One of the final products of pyroprocessing for spent nuclear fuel recycling is a U/TRU ingot consisting of rare earth (RE), uranium (U), and transuranic (TRU) elements. The amounts of nuclear materials in a U/TRU ingot must be measured as precisely as possible in order to secure the safeguardability of a pyroprocessing facility, as it contains the most(More)
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