On the study of the stress-strain state of the IVV.10M reactor vessel and in-vessel components under seismic impacts

The problem of the seismic stability of the new IVV.10M research reactor is considered. To computationally prove the viability of the engineering solutions, a detailed finite element model of a reactor is developed in strict accordance with the design documentation. The model represents the actual interrelations between all load-carrying elements and loads acting on the structure. A computational investigation of the stress-strain state of a reactor is carried out using the ANSYS bundled software. The natural oscillation frequencies and natural mode shapes of the structure are determined by linear-spectral analysis. The dynamic impacts occurring under seismic conditions are computed taking into consideration the actual response spectra. The most heavily loaded sectors in the reactor vessel and in-vessel components are established. A quantitative assessment of the stress-strain-state parameters in the crucial regions of the reactor is carried out. The computational results are compared with the figures of the normative documents currently in force in domestic nuclear-power engineering.     

Experimental modal analysis on the core support barrel of reactor internals using a scale model

The vibration of core support barrel (CSB) in a typical pressurized water reactor is studied by experimental and finite element analysis methods. Free vibration models are built and tested for the 1/13.7th scale of Ulchin Nuclear (UCN) Unit 3 & 4. Finite element model is established by plate model with shell elements. Finite element and measurement analyses are performed with respect to the two type of cylindrical shell models with and without holes. Test results on CSB vibration models are presented and compared with finite element analysis results. Various techniques are used to compare the measurement and analysis results.     

核电堆内构件在役维修用水下吸尘装置

主要介绍核电堆内构件在役检修用水下吸尘装置的原理、组成及功能。     

多层球形压力容器的弹塑性应力与强度可靠性分析

考虑材料的线性强化弹塑性性质,推导出了多层球形压力容器在弹塑性变形范围内的确定性应力解.然后基于“均值”和信息熵不变原则对影响容器强度的随机因素和模糊因素进行互相转换,分别采用随机可靠性和模糊可靠性方法计算分析了既含随机因素、又合模糊因素的压力容器的强度可靠性,结果表明随机和模糊可靠度相对误差仅为4.08％,且模糊可靠度更接近强度的确定性分析结果.     

360万t／年加氢裂化装置反应器吊装机具结构的有限元计算

由于加氢反应器设备单件重量大,吊装静载荷1245．5t,目前国内无法通过单台起重机吊装,为充分利用起重设备资源,采用了力矩分配装置,让型号为LR11350的1350t履带起重机与型号为LR1750的750t履带起重机联合主吊;为减少起重设备利用资源,吊装溜尾采用滑动摩擦尾排溜尾的吊装施工方法。     

钢制薄壁内压容器静强度最小安全系数的研究

考虑到容器静强度与载荷的不确定性,得到钢制薄壁内压容器的安全系数与试验压力系数,是创建压力容器可靠性设计理论的重要内容;根据容器静强度在最苛刻耐压试验时的许用可靠度,确定了容器在耐压试验和正常操作时的最小许用可靠度范围;得到了用于计算钢制薄壁内压容器静强度最小安全系数与试验压力系数的方法。     

On the burst strength and necking behaviour of rotating disks

The behaviour of an elastic-plastic rotating disk is analysed both in the context of three dimensional theory and within the framework of the plane stress approximation. For an axisymmetric disk the possibility of bifurcation into a non-axisymmetric mode is investigated. Computations are also made for the behaviour of a disk with initial imperfections either in the form of a thickness variation or in the form of material inhomogeneities. For a ductile, bored disk of uniform thickness it is found that bursting occurs after the critical bifurcation point, which may occur before or after the point of maximum angular velocity in the axisymmetric solution. Thus, necking has started to develop in the disk, when ductile bursting occurs.     

N中取M设计分析及其在反应堆保护系统中的应用

N中取M系统是反应堆保护系统中的冗余设计。通过分析系统拒动率、误动率两个量化指标,得到严格数学公式,并做了近似计算。基于公式,系统解释了工程实际中Ⅳ中取M多为4取2或3取2的基本原理。以非安全故障概率0．1、安全故障概率0．1为例,比较不同取值的判决系统。依据系统拒动率A、误动率B,单一模块拒动率P、误动率Q,即输入设计参数（A,B,P,O）,计算得到Ⅳ和M的取值。     

Assessment of floor response spectrum by parametric error estimation and its application to a spring-mounted reactor vessel assembly

For large facilities having several floors or containers, floor response spectra, FRS, other than ground response spectra need to be developed. However, FRS can have error especially when components are not small in their masses. In this paper, error is estimated in order to specify applicability of the FRS by deriving and comparing with analytic results for two degrees of freedom system. An identity regarding modal vectors and participation factors in the modal method is used to measure the FRS error. It is found that FRS is sufficiently accurate if the mass of a component is one hundredth or less than that of the floor. On the contrary, it is shown that fixed frequency of a component does not affect the FRS accuracy considerably. A compact power plant system consists of two main assemblies with spring mounts is applied as an example for the derivation of the FRS and several aspects associated with its modeling and calculation are discussed.     

On the problem of the strength of hydrojet cutting equipment

Abnormally rapid failure of domestic ultrahigh-pressure cylinders used for hydrojet cutting necessitated a new approach to establishing the causes of their rapid wear. An attempt to explain observed phenomena in terms of supercritical water was made, and a potential method of increasing the wear-resistance of the these cylinders by a special pressure testing process was suggested.     

Characteristics of the neutron field at the core center in the ИBB-2M water-moderated water-cooled reactor

The neutron spectrum has been measured at the center of the core in the ИBB-2M research water-moderated water-cooled reactor. A technique has been developed to measure the energy spectrum of neutrons in high-intensity fields (with a flux density of >10¹² cm^?2 s^?1) without recourse to fission detectors enclosed in boron shields.     

Contribution to the issue of evaluating the compressive strength of concrete exposed to high temperatures using the Schmidt rebound hammer

Concrete properties change as a result of ambient conditions. The internal microstructure changes under high temperatures. As a consequence, this change affects both physical and mechanical properties of concrete and therefore the parameters determined from nondestructive testing. It was determined that for concrete exposed to temperatures in the range of 200 to 400°C the rebound number measured by the rebound hammer is approximately 9% higher after heat load than for wet concrete placed in a standard environment. Temperatures from 600 to 800°C cause a drop in the rebound number, which correlates with a decrease in the concrete’s compressive strength. A strength dependency was established for the N-type Schmidt rebound hammer expressing the relationship between the rebound number and the compressive strength of concrete exposed to heat load, which is characterized by a high correlation between variables (correlation coefficient is 0.98). To estimate the compressive strength of concrete in a structure which has been exposed by fire, can be used both the calculated strength relationship, both the calibration curves for N-type Schmidt rebound hammer calculated by manufacturer, eventually the basic curve from CSN EN 13791. If the calibration equation for N-type Schmidt rebound hammer or basic curve of CSN EN 13791 is taken, the calculated strength for the rebound numbers should be lowered using the corrective coefficient, the value of which is 0.54, respectively 0.65.     

On the limit analysis of a spherical pressure vessel with fully circumferential defects

Using a circumscribing yield surface, the limit pressure is obtained for a spherical shell with a circumferential partial penetration defect. The theory indicates the importance of the transverse shear stress for deep defects and is in good agreement with experiments on four vessels that are also described.     

Evaluation of strength variation of domes and cylinders with different winding angle of type III high pressure storage vessel

Journal of Mechanical Science and Technology - Type III vessels are used to store gases at high pressure and, for efficient use, should be as light as possible without compromising stability....     

海洋船舶控制平台吊装平衡梁的设计

1概述 海洋船舶控制平台是一种大型非标设备，外形尺寸为9．8m×4．9m×3．4m，结构件全部由钢材制造，重量400kN，底座为型钢焊接结构件，安装有供吊装用的4个钢制吊耳，控制平台内外表面均涂装涂料，内部安装自动控制设备，价值昂贵，在吊装时要求平稳，无振动，无碰擦，保证控制平台和船舶的安全。     

Multibarrel injectors of fuel pellets for injection into plasmas of the HL-1M, HT-6M, and T-10 tokamaks

Injectors intended for studying the processes occurring in plasmas of small tokamaks upon injection of one to eight pellets of solid hydrogen or deuterium are described. The diameter of the pellets is determined by the caliber of the barrels used and ranges from 0.6 to 1.5 mm; their length and velocity are 1–5 mm and 0.5–1.4 km/s, respectively. Different methods for preparing pellets directly inside the injectors’ barrels have been analyzed.     

Computer-controlled testing system for investigating the dynamic characteristics of contactors with A.C. electromagnet drives

An original computer-controlled measurement system with electrodynamic sensor is presented in this paper. The system was used to examine simultaneously dependencies of time related electromagnet coil current, electromagnet coil voltage, electric power supplied to electromagnet coil, voltage across contacts, acceleration, speed, path and kinetic energy of contactor moving element. An additional software allows diagrams of the following parameters to be obtained: maximum and minimum acceleration, maximum speed and kinetic energy of contactor moving element, electric energy supplied to electromagnet coil and times typical of alternating current electromagnetic drive for selected values of the coil supply voltages and various switching on angles of this voltage (within the range 0–170°). Results of the investigation enable also to take a view on such parameters of the designed equipment as, for example, making time or rebounds of the contactor contacts. The system is very useful to verify the results of investigation of computer simulated contactor closing.