Association analysis of tissue inhibitor of metalloproteinase2 gene polymorphisms with COPD in Egyptians

AbstractProteinase/antiproteinase imbalance is recognized to play an important role in the pathogenesis of chronic obstructive pulmonary disease (COPD). A relative increase in the activities of matrix metalloproteinases might be caused by mutations of tissue inhibitor of metalloproteinase2 (TIMP2). Recently, two polymorphisms of the TIMP2 gene, +853 G/A and −418 G/C (+551 and −720 from the translation initiation site), have been shown to be associated with the development of COPD in the Japanese population. In this study, a case-control association analysis for these polymorphisms was conducted in the Egyptian population using 106 COPD patients and 72 healthy controls. The genotype frequency of +853 G/A was significantly different between the patient and the control groups (P=0.029), although no significant difference was detected in the allele frequency between the two groups. These results suggest that the +853 G/A polymorphism of the TIMP2 gene might be associated with COPD across ethnicities. In contrast, neither the distributions of genotype nor allele frequencies of –418 G/C were significantly different between the two groups, raising the possibility that a combination of different genetic factors contributes to the development of COPD in different ethnic groups

Hydrogen saturation influence on erosion behavior of thin W-films under steady state nitrogen plasma impact

The erosion behavior of W-Pd bimetallic system was examined for both hydrogen saturated and non-saturated states under impact of steady state nitrogen plasma of a mirror Penning discharge. Possible physical mechanism is discussed to explain the essential decrease of erosion rate and damages of such systems (form change, macro-blistering and macro-flaking) caused by hydrogen saturation to high concentration.Досліджувалося ерозійне поводження W-Pd біметалічних систем у насиченому воднем стані і ненасиченому, при впливі стаціонарної азотної плазми відбивного розряду Пеннінга. Обговорюються можливі фізичні механізми, що пояснюють істотне зниження швидкості ерозії й ушкодження таких систем (зміна форми, макро- блістерінг і макро-флекінг), обумовлених насиченням воднем до високих концентрацій.Исследовалось эрозионное поведение W-Pd биметаллических систем в насыщенном водородом состоянии и ненасыщенном, при воздействии стационарной азотной плазмы отражательного разряда Пеннинга. Обсуждаются возможные физические механизмы, объясняющие существенное снижение скорости эрозии и повреждения таких систем (изменение формы, макро-блистеринг и макро-флэкинг), обусловленных насыщением водородом до высоких концентраций

Kinetics of hydrogen permeation through W-Pd bimetallic systems

The experimental investigations had been carried out of the kinetics of hydrogen permeation through W-Pd bimetallic systems. The possible mechanisms had been suggested and analyzed to explain the observed anomalies in the hydrogen permeation behavior of such systems, on the assumption of measured isotherms and isobars of hydrogen permeability, energy state of hydrogen in W-Pd system, and theory of hydrogen diffusion in the systems, which contains large number of closed and interconnecting poresПроведено експериментальні дослідження кінетики проникнення водню через W-Pd біметалічні системи. Запропоновано можливі механізми для пояснення виявлених аномалій у поводженні воднепроникнення таких систем, виходячи з обмірюваних ізотерм і ізобар проникнення водню, енергетичного стану водню в системі W-Pd і теорії дифузії в системах з великою кількістю замкнутих і сполучених пор.Проведены экспериментальные исследования кинетики проникновения водорода через W-Pd биметаллические системы. Предложены возможные механизмы для объяснения обнаруженных аномалий в поведении водородопроницаемости таких систем, исходя из измеренных изотерм и изобар водородопроницаемости, энергетического состояния водорода в системе W-Pd и теории диффузии в системах с большим количеством замкнутых и сообщающихся пор

Phenotyping of type II and IV hyperlipoproteinemias by a simple, quantitative agarose gel lipoprotein electrophoresis

From the statistical analysis of the densitometric percentage counts derived from 97 lipoprotein electrophoreses from patients with Type II or Type IV hyperlipoproteinemia, we developed a simple sequential screening approach. The method is highly accurate in assigning patients to their proper diagnostic classification. Also, the method is nonparametric, i.e., distribution-free, and considers one variable at a time for discrimination. This method, apart from sampling errors, does not give misclassified patients, but may give some undecided cases

Nuclear modules of ITER tokamak systems code

Nuclear modules were developed to model various reactor components in the ITER systems code. Several design options and cost algorithms are included for each component. The first wall, blanket and shield modules calculate the beryllium zone thickness, the disruptions results, the nuclear responses in different components including the toroidal field coils. Tungsten shield/water coolant/steel structure and steel shield/water coolant are the shield options for the inboard and outboard sections of the reactor. Lithium nitrate dissolved in the water coolant with a variable beryllium zone thickness in the outboard section of the reactor provides the tritium breeding capability. The reactor vault module defines the thickness of the reactor wall and the roof based on the dose equivalent during operation including skyshine contribution. The impurity control module provides the design parameters for the divertor including plate design, heat load, erosion rate, tritium permeation through the plate material to the coolant, plasma contamination by sputtered impurities, and plate lifetime. Several materials: Be, C, V, Mo, and W can be used for the divertor plate to cover a range of plasma edge temperatures. The tritium module calculates tritium and deuterium flow rates for the reactor plant. The tritium inventory in the fuelers, neutral beams, vacuum pumps, impurity control, first wall, and blanket is calculated. Tritium requirements are provided for different operating conditions. The nuclear models are summarized in this paper including the different design options and key analyses of each module. 39 refs., 3 tabs