Thermal characterisation of ceramic/metal joining techniques for fusion applications using X-ray tomography

This work investigates the thermal performance of four novel CFC–Cu joining techniques. Two involve direct casting and brazing of Cu onto a chromium modified CFC surface, the other two pre-coat a brazing alloy with chromium using galvanisation and sputtering processes. The chromium carbide layer at the interface has been shown to improve adhesion. Thermal conductivity across the join interface was measured by laser flash analysis. X-ray tomography was performed to investigate micro-structures that might influence the thermal behaviour. It was found that thermal conductivity varied by up to 72%. Quantification of the X-ray tomography data showed that the dominant feature in reducing thermal conductivity was the lateral spread of voids at the interface. Correlations were made to estimate the extent of this effect

Operating a full tungsten actively cooled tokamak: overview of WEST first phase of operation

WEST is an MA class superconducting, actively cooled, full tungsten (W) tokamak, designed to operate in long pulses up to 1000 s. In support of ITER operation and DEMO conceptual activities, key missions of WEST are: (i) qualification of high heat flux plasma-facing components in integrating both technological and physics aspects in relevant heat and particle exhaust conditions, particularly for the tungsten monoblocks foreseen in ITER divertor; (ii) integrated steady-state operation at high confinement, with a focus on power exhaust issues. During the phase 1 of operation (2017–2020), a set of actively cooled ITER-grade plasma facing unit prototypes was integrated into the inertially cooled W coated startup lower divertor. Up to 8.8 MW of RF power has been coupled to the plasma and divertor heat flux of up to 6 MW m−2 were reached. Long pulse operation was started, using the upper actively cooled divertor, with a discharge of about 1 min achieved. This paper gives an overview of the results achieved in phase 1. Perspectives for phase 2, operating with the full capability of the device with the complete ITER-grade actively cooled lower divertor, are also described

Prediction of test anxiety and academic self-handicapping based on alexithymia

Background : The aim of this study was to predict the test anxiety and academic self-handicapping based on alexithymia in students with reading learning disorder. Materials and Methods: This study is a correlational study. The population included all of students with reading disorder in Khorramabad city in 2015-2016. Cohen&rsquo;s Proposed Method was used for determining the size of the sample,and among the students who referred to&nbsp; education center in Kohrramabad, based on specialist's diagnosis in this field, in sum 112 students carried criteria for participating in this study. The students completed the test anxiety, self handicapping and alexithymia questionnaires. Regression analysis was used for analyzing data. The data were analyzed by statistical SPSS software version 18. Results: The results showed that the correlation between study variables were significant (p>0.001). Also, The results of regression analysis showed that alexithymia was able to predict ( 54/. P<0.001) the total variance of test anxiety and academic self-handicapping. Conclusion: The results can help to counsolers and workers in the education field for effective interventions in test anxiety and academic self-handicapping

The effect of positive therapeutic program on psychological well-being of women with ADHD children

Background: The present study was to evaluate effectiveness of positive therapeutic program on psychological well-being in women with ADHD children. Materials and Methods: &nbsp;This study was quasi-experimental and pretest-posttest with control group kind. The study sample consisted of 50 mothers in 2015-2016. Convenience sampling was applied to select the participants. Participants were quite randomly divided into two groups of 25 individuals. These groups were randomly divided into two groups of experimental and control groups. The experimental group received positive program and the control group received no intervention. The therapeutic packages of the positive were conducted for six sessions. Before and after the experiment all of the participants responded to the psychological well-being questionnaire. Three months after the experiment, i.e. the follow-up stage, in order to check storage of the program's effects, the participants answered the instrument. The data were analyzed by covariance (MANCOVA) test using SPSS 18.0. Results: The results of this study showed that positive program resulted significant effect in all of six components of psychological well-being. It should be noted that all of the results were significant at (p< 0.05) (DF 48, 2) and its effect maintain three months after the experiment (p< 0.05). Conclusion: Regarding to results, the positive therapeutic program can be effective in decreasing psychological problems. Also, this program is useful in promoting mental health among mothers with psychological problems such as ADHD.&nbsp

ITER Relevant High Heat Flux Tests on Plasma Facing Surfaces

The current ITER design employs beryllium, carbon fiber reinforced composite and tungsten as plasma facing materials. Since these materials are exposed to high heat fluxes during the operation, it is essential to perform high heat flux tests for R&D of ITER components. Static heat loads corresponding to cycling loads during normal operation, are estimated to be up to 20MW/m(2) in the divertor targets and around 0.5 MW/m(2) at the first wall in ITER. For the static high heat flux testing, tests in electron beam facilities, particle beam facilities, IR heater and in-pile tests have been performed. Another type, more critical heat loads, which have high power densities and short durations, corresponding to transient events, i.e. plasma disruption, vertical displacement events (VDEs) and edge localized modes (ELMs) deliver considerable heat flux onto the plasma facing materials. For this purpose, tests in electron beam (short pulses), plasma gun and high power laser facilities have been carried out. The present work summarizes the features of these facilities and recent experimental results as well as the current selection of ITER plasma facing components