Limit Analysis for the Mechanical Structure of the ITER Neutron Shielding Block

The ITER neutron shielding blocks are located between the inner shell and the outer shell of the vacuum vessel （VV） with the main function of providing neutron shielding. Conskicring the combined loads of the shielding blocks during the plasma operation of the ITER, limit analysis for one typical ferromagnetic （FM） shielding block has been performed and the structural design has bccn evaluated based on the American Society of Mechanical Engineers （ASME） criterion and European standards. Results show that the collapse load of this shielding block is three times the specified load, which is much higher than the design requirement of 1.25. The structure of this neutron shielding block has a sufficient safety margin.

Numerical Analyses of Electromagnetic Forces on the ITER Blanket Module Shield Block During Major Disruptions

Electromagnetic（EM） load is one of the key design drivers for the blanket shield block（SB） and other in-vessel components. In this article, an EM analysis method was developed to address the EM force on the SB. The plasma currents, which vary spatially and temporally,are loaded as a filament at each time point. The standard blanket module No.04（BM04） under major disruption（MD） is selected to perform the analyses. The analyses results are validated by comparing currents on the passive structure. To better understand the effects of cooling channels and slits on the EM force, the case of SB without cooling channel and the case without slits are calculated to make comparisons. The results show that the slits play an important role in controlling the EM load on SB.

Preliminary Design and Analysis of ITER In-Wall Shielding

ITER in-wall shielding （IIS） is situated between the doubled shells of the ITER Vacuum Vessel （IVV）. Its main functions are applied in shielding neutron, gamma-ray and toroidal field ripple reduction. The structure of IIS has been modelled according to the IVV design criteria which has been updated by the ITER team （IT）. Static analysis and thermal expansion analysis were performed for the structure. Thermal-hydraulic analysis verified the heat removal capability and resulting temperature, pressure, and velocity changes in the coolant flow. Consequently, our design work is possibly suitable as a reference for IT＇s updated or final design in its next step.

真空氦检漏技术在ITER项目中的应用

包层屏蔽块是国际热核聚变实验堆(ITER)项目的重要组成部件。每个屏蔽块都需要进行真空热氦检漏,以确保其密封性能。提出了一种利用真空热氦检漏系统进行高灵敏度检测的方法,该系统可以使包层屏蔽块去除自身的杂质气体来规避干扰,并通过提高环境温度和屏蔽块内部和外部之间压力差的方式来提高氦原子的活性以提高检测灵敏度。该方法可在检测环境温度为250℃,环境压力为1×10^(-5)Pa,产品内部氦气压力为4 MPa的条件下,实现系统灵敏度为10-11Pa·m^(3)·s^(-1)数量级的氦气泄漏检测。试验结果表明,该技术具有高自动化和数据可追溯的优点,可避免产品自身释放的杂质气体带来的影响,对细微泄漏具有较高的检测灵敏度。

ITER屏蔽包层屏蔽块热工水力分析

通过ANSYS CFX对ITER屏蔽块进行了热工水力分析,对同一计算模型给出了两套不同的网格,分析了网格对计算精度的影响,结果表明两套网格都有较好的计算精度。通过数值模拟分析了壁面粗糙度对流动及传热的影响,结果表明壁面粗糙度是影响传热的一个非常重要的因素。

ITER包层屏蔽块全尺寸原型件的设计与关键制造技术的研发

ITER包层屏蔽块全尺寸原型件应基于当前的设计方案,满足其物理功能,并符合包层界面的设计要求。另外,在屏蔽块全尺寸原型件的设计中,还要充分考虑关键制造技术的研发结果,例如深孔钻、TIG焊接、NDT检测等技术,这些关键制造技术的研发结果,为设计提供了技术保障。该全尺寸原型件的顺利完成并通过ITER相应认证程序,是中方签署采购的必由环节,也为今后完成采购包奠定了基础。

ITER屏蔽块冷却通道热工水力分析与设计改进

屏蔽块是国际热核聚变实验堆(ITER)的重要组成部分之一,其结构设计尤其是内部冷却剂通道设计将直接影响屏蔽块的冷却效果及模型的安全性。运用计算流体力学(CFD)软件对屏蔽块模型进行热工水力计算,根据计算结果提出改进建议,并对改进后的模型重新进行数值分析。结果表明:屏蔽块的进出口段压降减小,冷却剂流动总压降减小;主要冷却支管的流量分配和流速分布更加均匀;屏蔽块表面局部最高温度大大降低,可避免由于冷却不均造成模块热应力过大。

ITER屏蔽块真空热氦检漏装置热工水力学设计与分析

对ITER包层屏蔽块进行了热工水力学设计及分析,并给出了两套合理的加热方案。分析结果表明,可以通过分阶段改变入口气体温度的方法实现在高效加热屏蔽块的同时满足工程及部件热应力的技术要求,并通过热应力计算验证了加热过程不会对屏蔽块产生不可预期的结构破坏。

ITER中子屏蔽块结构分析中力矩补偿问题的探讨

国际热核聚变反应堆(ITER装置)的中子屏蔽块分布于超导托卡马克真空室双层壳体内部,用于屏蔽核聚变产生的中子。中子屏蔽块在正常工作状况下将受到重力、涡流电磁力和地震载荷等影响。为校核其结构强度,对其受力进行整体结构分析。在中子屏蔽块的结构分析过程中,由涡流引起的电磁力所产生的力矩与所给定力矩的大小不相同。为了使其结构分析能模拟真实工况,分析的结果更准确,分析过程中采用了添加力矩补偿的方式。文中运用ANSYS软件分别对中子屏蔽块添加力矩补偿和不添加力矩补偿两种方法进行结构分析,并对分析结果进行比较。结果表明,补偿力矩的添加对屏蔽块各附件的应力大小影响很大,因此用力矩补偿方法分析得到的结果更能保证分析结果的准确性,且使中子屏蔽块设计的安全性和可靠性大大提高。此方法可为同样有力矩存在的结构分析提供有力的参考依据。