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Variation in the patellar tendons moment supply discovered by having an enhanced measurement construction.
The light collection efficiency of plastic scintillator panels used in radiation portal monitors (RPM) declines over time. We present an efficiency calibration procedure to measure the capability of an aged panel to detect 186 keV gamma rays of highly enriched uranium (HEU). The method is based on a coincidence measurement of backscattered Cs-137 gamma rays having an energy of 184 keV. Energy calibration of the plastic panel can be obtained from the same measurement. In this paper we present the impact of variability, a surface source parameter, on the efficiency evaluation of surface contamination monitors. This study was based on two source uniformity correction methodologies and data from real surface source distributions. Surface source intensity distribution has been changed by rearranging the cells (portions of the active area of each LARS) while keeping the same source uniformity value. selleck chemicals Instrument efficiencies have been calculated for different sets of uniformities and variabilities. This study led to emphasize the importance of variability, a differential source intensity distribution parameter, over the uniformity, an integral source intensity distribution parameter, and reinforced the importance of the source uniformity correction procedure on the course of surface contamination monitor calibration. Source location of Special Nuclear Material (SNM) encompassing 95% 235U and 239Pu is identified by utilizing a directional source from Patent No US20190013109A1 using Prompt Gamma Neutron Activation Analysis (PGNAA) and neutron spectroscopy simulated with Monte-Carlo N-Particle transport 6.2 (MCNP). BC-408, HPGe, LaBr3 detector arrays were used to identify the location of the SNM using total counts incident on each detector, and PGNAA photopeaks from HPGe and LaBr3 detector arrays in a polyethylene shield. The conducted simulations varied the volume and location of the SNM in the MCNP input files to observe how the source location method behaved. PGNAA photopeaks used for source identification include 61 keV from fission, 2.223 MeV prompt gamma from hydrogen, 511 keV annihilation, and a single and double escape peaks from the prompt gamma interaction from hydrogen. The capabilities of each detector systems to acquire well resolved photopeaks with a 1% relative error or less, and total relative error for F4 and F8 tallies were less than 0.015% relative error. Source predictions of the SNM with uneven amounts of polyethylene shielding between the source and detectors was observed to overpredict and give invalid source location predictions. Source locations of the SNM with even amounts of polyethylene material between the source and each detector were found to be valid. With a 1 Ci 241Am source activity, it was determined that 1630 s were needed to obtain the results for each detector system with the quasi-forward directional AmBe source. Coupling source and material identification together would increase acquisition time but would only require one system to determine. Radiation therapy has an irreplaceable role in modern oncologic therapy, thanks to the advanced radiation techniques developed in recent decades. However, photon-resistant cases are sometimes encountered. Boron Neutron Capture Therapy (BNCT) is a highly selective radiotherapy technique due to the high tumor to tissue ratio of boronophenylalanine (BPA), the unique medication used for the BNCT treatment reaction. In this study, we report on three special patients with malignant brain tumors treated with BNCT. 231Pa is the longest-lived decay product in the 235U decay chain and precise standards of this radionuclide are required to enable accurate, traceable measurements in nuclear dating applications such as geochronometry and nuclear forensics. Three independent techniques were used at NPL to determine the activity per unit mass of a freshly separated 231Pa solution as part of an international CCRI(II) comparison CCRI(II)-K2.Pa-231.The first method was defined solid angle α counting and is the first result reported in a BIPM comparison with this instrument. The second method was 4πα liquid scintillation (LS) counting combined with the CIEMAT/NIST method using commercially available LS counters. The third technique used was 4π(LS)α-γ coincidence counting on an NPL-built system comprising an LS counter with dual photomultiplier tubes (PMTs) coupled to a 70% relative efficiency HPGe γ-spectrometer. Excellent agreement between the three methods was obtained. This study explores the effect of 229Th tracer tail interference on the determination of the sensitivity of 230Th alpha spectrometry of samples with environmental levels of radioactivity. Tracer peak tail interference was calculated with Suma-Alpha, whilst Visual Basic for Applications (VBA in Excel©) software was used to study the variation in sensitivity in terms of the amount of tracer added. Unnecessary increases in the amount of tracer or extended sample measuring times were observed to have adverse effects on method sensitivity (Detection Limit- Ld). The absolute activity of 18F was determined using 4πβ-γ liquid scintillation coincidence counting using beta-efficiency extrapolation. An ionization chamber factor was determined for use during a SIRTI comparison, for which results are presented. A non-extrapolation method based on a detection efficiency analysis was also employed using an adaptation of the double-phototube coincidence efficiency for a threshold above the second monopeak. Results and uncertainty budgets for the two methods are presented and discussed. Mechanisms of energy absorption in solid disordered neon under 4 to 800 Ry photon irradiation are studied by Monte Carlo simulation with accounting for the cascade decays of vacancies produced by primary and secondary ionization processes. The dominating channel for the transfer of energy to the sample giving about 55% of total absorbed energy is through ionization and excitation of atoms of the medium by secondary electrons produced by primary photoionization and secondary inelastic processes, and by vacancy decay cascades. The portion of energy absorbed in the acts of primary photoionization is significant only at incident photon energies fewer than 10 Ry, it is about 5% at incident photon energy near the Ne1s ionization threshold, and decreases rapidly at higher photon energies. The energy absorbed in secondary photoionization processes makes 3-5% of total absorbed energy on the whole incident photon energy interval. About 40% of total absorbed energy is transferred by low-energy electrons and photons that cannot ionize or excite atomic electrons.
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