OBJECTIVE:This study retrospectively analysed the impact of self-care education based on Orem's self-care deficit theory on elderly male patients with prostate cancer (PCa). METHODS:Medical records of elderly male patients admitted to our hospital for PCa from January 2021 to January 2024 were retrospectively collected. Patients were divided into two groups on the basis of the nursing approach: The Orem group (receiving self-care education that is based on Orem's self-care deficit theory) and the conventional group (receiving routine nursing care). Self-efficacy, quality of life (QOL), psychological health and nursing satisfaction were compared between the two groups. RESULTS:A total of 86 male patients with PCa were included in the study (Orem group n = 41, conventional group n = 45), with no statistically significant differences in age, tumour staging, comorbidities nor other general medical history between the two groups (p > 0.05). After 6 months of nursing care, both groups showed improvements in self-efficacy, QOL and psychological health. However, the Orem group demonstrated better scores in all aspects, with statistically significant differences (p < 0.05). The nursing satisfaction rate in the Orem group was 90.24%, which was superior to the 75.56% of the control group, and the difference was statistically significant (p < 0.05). CONCLUSIONS:Compared with the traditional routine nursing care, self-care education based on Orem's self-care deficit theory can effectively improve the self-efficacy, QOL and psychological health of elderly patients with PCa. It is worth promoting in clinical practice.

The J-TEXT capability is enhanced compared to two years ago with several upgrades of its diagnostics and the increase of electron cyclotron resonance heating (ECRH) power to 1 MW. With the application of electron cyclotron wave (ECW), the ECW assisted plasma startup is achieved; the tearing mode is suppressed; the toroidal injection of 300 kW ECW drives around 24 kA current; fast electrons are generated with toroidal injected ECW and the runaway current conversion efficiency increases with ECRH power. The mode coupling between 2/1 and 3/1 modes are extensively studied. The coupled 2/1 and 3/1 modes usually lead to major disruption. Their coupling can be either suppressed or avoided by external resonant magnetic perturbation fields and hence avoids the major disruption. It is also found that the 2/1 threshold of external field is significantly reduced by a pre-excited 3/1 mode, which can be either a locked island or an external kink mode. The disruption control is studied by developing prediction methods capable of cross tokamak application and by new mitigation methods, such as the biased electrode or electromagnetic pellet injector. The high-density operation and related disruptions are studied from various aspects. Approaching the density limit, the collapse of the edge shear layer is observed and such collapse can be prevented by applying edge biasing, leading to an increased density limit. The density limit is also observed to increase, if the plasma is operated in the poloidal divertor configuration or the plasma purity is increased by increasing the pre-filled gas pressure or ECRH power during the start-up phase.

Collisional-merging is a way to form high-performance field-reversed configuration (FRC) plasma. An experiment device named HUST-FRC (HFRC) is under construction in Huazhong University of Science and Technology, which will be used to investigate the FRC formation through collisionalmerging. In this research, a magnetohydrodynamics simulation software called USim is used to study the effect of the initial density of plasma, the amplitude of the bias magnetic field, the configuration of the bias field, the rise time of the main field and the magnetic field ripple on the plasma parameters to facilitate the design and operation of HFRC. Preliminary simulation results show that cusp configuration, lower ripple, higher initial density, an initial bias field of −0.15 T or −0.2 T, and a rise time of 4 μ s are conducive to the formation of high-performance FRC plasma in the HFRC device.

针对目前数字孪生车间构建中工业机器人等虚拟实体建模复杂、开发周期长等问题,提出了一种数字孪生车间工业机器人虚实驱动系统的模块化构建方法,即将虚实驱动系统分为设置模型参数的交互层和按功能需求设计配置的控制层,然后将实体工业机器人等抽象为单功能原子模型耦合而成的仿真模型.模块化分层构建虚实驱动系统的方法能快速有效地实现工业机器人等数字孪生虚拟实体的建模,以及工业机器人在虚拟空间中的仿真运行模拟和虚实同步运行.

虚拟实体是数字孪生五维模型中重要的组成部分,其行为模型描述了物理实体在外部环境与内部运行机制作用下的实时响应及行为.针对离散制造车间数字孪生虚拟实体行为模型缺乏统一描述与精确定义的难题,提出一种使用基于值的离散事件系统规范(VDEVS)对行为模型进行描述的方法.在原有数字孪生五维模型基础上定义了数字孪生车间虚拟实体分层模型,实现了其与数字孪生车间物理实体的一一映射.通过对传统离散事件系统仿真规范(DEVS)进行扩展提出了VDEVS,从而更加精确地描述离散制造车间复杂系统级、系统级、单元级虚拟实体的行为.最后,针对某加工单元,利用基于VDEVS的方法对其行为模型进行了描述.

The HUST field-reversed configuration (HFRC) is a field reversed plasma research device based on colliding and merging under design. To increase the parameters of the initial plasma formed in the theta-pinch, the theta-pinch is designed with very high parameters, namely a chamber diameter of 0.6 m, a bias magnetic field of -0.16 T, a preionization frequency of 150 kHz, and a main magnetic field of 0.6 T. To control the plasma formation and ejection, the discharge regulating accuracy for the theta-pinch is required within several microseconds. Thus, a high voltage, high current pulsed power supply with high controllability is required to satisfy the physical design. This article mainly presents the challenges and solutions in the design of the power supply system. First, 18 theta-pinch coils are used for the field generation to reduce the current on each coil, which results in design parameters of 70 kV/86 kA for the power supply. Then, a new topology with two power supply modules connected in series is adopted to feed the coil, which reduces the system voltage level and increases the operational reliability. Besides, hydrogen thyratron is adopted as the pulsed switch, and a corresponding trigger circuit based on insulated gate bipolar transistor (IGBT) is designed to ensure the precise control of the sequential discharge. Experimental tests are also performed on the thyratron and its trigger circuit, and the breakdown delay time is proven to be less than 1 mu s. In conclusion, the designed power supply system can satisfy the requirements of high operation parameters and high controllability.

Recent J-TEXT research has highlighted the significance of the role that non-axisymmetric magnetic perturbations, so called three-dimensional (3D) magnetic perturbation (MP) fields, play in a fundamentally 2D concept, i.e. tokamaks. This paper presents the J-TEXT results achieved over the last two years, especially on the impacts of 3D MP fields on magnetohydrodynamic instabilities, plasma disruptions and plasma turbulence transport. On J-TEXT, the resonant MP (RMP) system, capable of providing either a static or a high frequency (up to 8 kHz) rotating RMP field, has been upgraded by adding a new set of 12 in-vessel saddle coils. The shattered pellet injection system was built in J-TEXT in the spring of 2018. The new capabilities advance J-TEXT to be at the forefront of international magnetic fusion facilities, allowing flexible study of 3D effects and disruption mitigation in a tokamak. The fast rotating RMP field has been successfully applied for avoidance of mode locking and the prevention of plasma disruption. A new control strategy, which applies pulsed RMP to the tearing mode only during the accelerating phase region, was proved by nonlinear numerical modelling to be efficient in accelerating mode rotation and even completely suppresses the mode. Remarkably, the rotating tearing mode was completely suppressed by the electrode biasing. The impacts of 3D magnetic topology on the turbulence has been investigated on J-TEXT. It is found that the fluctuations of electron density, electron temperature and plasma potential can be significantly modulated by the island structure, and a larger fluctuation level appears at the X-point of islands. The suppression of runaway electrons during disruptions is essential to the operation of ITER, and it has been reached by utilizing the 3D magnetic perturbations on J-TEXT. This may provide an alternative mechanism of runaway suppression for large-scale tokamaks and ITER.