Validation of R5 assessment procedure for ITER test blanket module by finite element analysis

Part of the ITER experimental setup will be testing of the first wall blanket module built from EUROFER 97 steel. Lifetime of this component should be predicted with help of defect assessment procedure. This work verifies the application of the R5 assessment code on the 2D test blanket module geometry by using finite element simulations. Verification is based on the evolution of C(t) parameter. Results exhibit good correspondence in predictions provided by R5 and finite element method for different thermo-mechanical loading conditions. These results therefore show applicability of R5 procedure on such complex geometries.     

ITER双功能液态锂铅实验包层系统故障模式影响分析

实验包层模块允许放置在ITER中实验的前提是其对ITER的安全以及对工作人员和环境不构成显著影响。ITER要求各参与方的实验包层模块在实验前必须提交安全分析报告,进而获取安全许可证。在中国双功能锂铅实验包层模块(DFLL-TBM)设计基础上,采用了故障模式影响分析(FMEA)方法对DFLL-TBM进行了安全评估与分析,得到所有可能导致严重后果的假设始发事件,验证了确定论安全分析所选择的三个参考事件可以包络所有的假设始发事件。     

Panel Report to FESAC: Review of the 1996 ITER Detailed Design Report

This report presents the results of a U.S. review of the 1996 Detailed Design Report (DDR) of the International Thermonuclear Experimental Reactor (ITER) project. It was prepared by a panel established by the U.S. Department of Energy (USDOE) Fusion Energy Sciences Advisory Committee (FESAC) and was subsequently endorsed by FESAC and provided to the USDOE. Copies of the charge and transmittal letters are incorporated at the end of this paper. Also incorporated in this paper are the reports of several subpanels established to provide detailed review and recommendations on specific topics. The authors of those subpanel reports are acknowledged in the text. The ITER was subsequently reduced in size and scope; this review refers to the full-size ITER design as it was completed in 1996.     

Study on three-dimensional heterogeneous calculation of ITER test blanket module with deterministic method

The neutronics analysis on the test blanket module (TBM) has important significance for the ITER device and its related experiment design. Quantities of scoping-type studies and conceptual designs were published by using the Monte Carlo method. However, disadvantages like time consuming make it necessary to develop a new highly efficient method. Hence, a new two-step approach method based on the 3D deterministic method for analyzing the TBM is proposed in this paper. A code package 3DMOC-NSPn was developed. It is mainly composed of three modules, the 3DMOC for generating the homogenization cross section; the LINK code for cross section condensation and the NSPn code for blanket calculation. The detailed flux distribution throughout the whole TBM and the mainly neutronics features, such as TBR, displacement per atom (DPA), helium and hydrogen production rate can be obtained. To validate the numerical approach and the code package, the calculations on China dual functional lithium lead-test blanket module (DFLL-TBM) was performed. The reference results were obtained by using the MCNP code. The numerical results from 3DMOC-NSPn are in good agreement with the references. It indicates that the whole code package is a reliable neutronics analysis tool for the TBM design and evaluation.     

ITER中国液态锂铅实验包层模块活化特性分析与废料处理

使用中子学程序系统VisualBUS和活化数据库EAF-99对DFLL-TBM的高级子模块DLL-TBM的活化特性进行了计算和分析,包括DLL-TBM各部件在不同停堆时间的活度、衰变余热和剂量率.活化计算所需要的三维中子能谱通过MCNP/4C中子/光子输运程序和国际原子能机构发布的FEND1.0数据库计算得到.在活化计算分析的基础上,参照欧洲聚变堆安全和环境评估(SEAFP)策略中有关核废料的处理标准评估了TBM各区材料在退役后的废料处理工作,包括核废料应该采用何种适当的方式进行处理及其被完全清除干净的可行性.     

ITER中国液态锂铅实验包层模块热工水力学设计与分析

依据ITER堆芯物理参数和中子学计算结果,给出了双功能锂铅实验包层模块热工水力学设计方案,并对氦气系统和液态金属锂铅系统压降和驱动功率进行了初步计算.相关中子学、结构、安全及MHD模拟结果证实了设计方案的可行性.     

ITER中国液态锂铅实验包层模块结构设计与加工

根据ITER实验包层的发展目标,实验要求,限制条件,结合聚变发电反应堆FDS-Ⅱ DLL/SLL包层方案设计了DFLL-TBM原型结构,给出了加工工艺和装配序列方案.该实验模块特点是极向LiPb流道易于布置FCI流道插件,"]"型隔板和"盒形"背板式联箱简化冷却方案和结构.这种简单的结构易于加工制造,易于派生出在ITER不同运行阶段实验的系列模块,符合在ITER进行SLL-TBM和DLL-TBM两种包层模块实验的策略.     

ITER中国液态锂铅实验包层模块设计研究与实验策略

在广泛调研和深入分析国际聚变堆包层发展状况的基础上,根据液态锂铅包层一般特点和中国发展的系列液态锂铅包层概念设计,提出了一个具有演示氦气单冷却剂和氦气/锂铅双冷却剂包层技术的双功能包层模块实验系统方案,对其性能进行了分析研究,作为中国向ITER实验包层工作组(TBWG)提交的液态包层实验模块最终设计描述文件的内容框架。总结了该工作主要内容,包括基本设计思想和方案描述、性能分析概况、对辅助系统的要求和实验策略与关键技术等。     

New progress on design and R&D for solid breeder test blanket module in China

ITER will be used to test tritium breeding module concepts, which will lead to the design of DEMO fusion reactor demonstrating tritium self-sufficiency and the extraction of high grade heat for electricity production. China plans to test the HCCB TBM modules during different operation phases. Related design and R&D activities for each TBM module with the auxiliary system are introduced.The helium-cooled ceramic breeder (HCCB) test blanket module (TBM) is the primary option of the Chinese TBM program. The preliminary conceptual design of CN HCCB TBM has been completed. A modified design to reduce the RAFM material mass to 1.3 ton has been carried out based on the ITER technical requirement. Basic characteristics and main design parameters of CN HCCB TBM are introduced briefly. The mock-up fabrication and component tests for Chinese test blanket module are being developed. Recent status of the components of CN HCCB TBM and fabrication technology development are also reported. The neutron multiplier Be pebbles, tritium breeder Li₄SiO₄ pebbles, and structure material CLF-1 of ton-class are being prepared in laboratory scale. The fabrication of pebble bed container and experiment of tritium breeder pebble bed will be started soon. The fabrication technology development is proceeding as the large-scale mock-up fabrication enters into the R&D stage and demonstration tests toward TBM testing on ITER test port are being done as scheduled.     

ITER双功能液态锂铅实验包层系统PIE-PIT分析

ITER要求各参与国的实验包层模块在实验前必须提交安全分析报告(含确定论分析和概率论分析),进而获取安全许可证.结合中国双功能锂铅实验包层模块的具体特点,采用了假设始发事件-潜在影响表(PIE-PIT)分析方法对DFLL-TBM进行了安全评估与分析,已验证确定论安全分析所选择的三个参考事件是否可包络PIE-PIT分析得到的严重事故序列.     

ITER中国液态锂铅实验包层模块氦气冷却系统初步设计研究

氦气冷却系统是ITER中国液态锂铅实验包层模块(DFLL-TBM)在ITER装置内进行实验的重要辅助系统.根据ITER运行时的热工条件、安全要求、空间要求,分析了DFLL-TBM氦气冷却系统的功能,确定氦气冷却系统的设计原则和要求,在此基础上给出氦气冷却系统的初步设计方案和设备布置.该氦气系统的特点体现在:双功能,即有宽的裕量满足SLL-TBM和DLL-TBM实验;两条氦气回路共享压力控制单元和氦气净化子系统;旁路设计调节TBM和热交换器氦气的出口温度.     

ITER中国液态锂铅实验包层模块中子学分析

基于ITER装置全模型,借助于MCNP自动建模程序MCAM,将TBM模块插入该模型的赤道窗口,使用MCNP/4C和FENDL1.0数据库,对DLL和SLL两个典型子模块设计进行三维中子学计算和分析,给出TBM模块核热功率密度分布以及氚增殖能力.     

ITER过渡馈线辅助支撑结构设计及传热计算

过渡馈线系统是为ITER磁体系统提供能量、制冷剂、进行测量诊断等服务的子系统。本工作对过渡馈线直线段内部辅助支撑和S弯箱内部辅助支撑等进行了设计,并借助ANSYS有限元分析软件[JP2]对过渡馈线直线段内管由辅助支撑引起的传导热进行了分析。结果表明,辅助支撑结构的设计是合理的。     

ITER氚增殖实验包层设计研究进展

国际热核实验反应堆(ITER)为人类开发聚变能提供重要的物理和工程技术实验平台,ITER氚增殖实验包层模块(TBM)技术是必须掌握的关键技术.参与ITER计划的成员国根据本国商用演示堆包层发展策略,分别提出了各自的实验包层概念,以便在ITER运行期间进行实验.本文对ITER-TBM目前已经开展和正在进行的主要设计研究工作进展进行总结,介绍了各方提出的设计方案、支撑设计的相关技术研究进展,以及合作实验窗口的分配现状.     

ITER10kA电流引线高温超导段研究

国际热核实验反应堆(ITER)高温超导电流引线（HTSCL）的特点是不仅电流容量大,且安全性要求非常高,高温超导段是HTSCL的关键部件。本文论述了ITER10kA电流引线高温超导叠和超导组件的真空钎焊工艺,分析了高温超导段漏热,并对高温超导段漏热和电流引线在10kA下的安全性参数进行了测试。结果表明,电流引线不仅漏热小,且安全裕度大,满足ITER设计要求。     

ITER中国液态锂铅实验包层模块氚渗透分析

对ITER中国液态锂铅实验包层模块的氚渗透途径进行了初步分析,并建立了氚渗透模型;在确保环境安全的前提下,通过计算LiPb中的氚分压分析了氚渗透量及氚总量的分配情况;在此基础上通过改变进入氚提取系统中LiPb比例(F)和涂层氚渗透减少因子(TPRF)对氚提取及渗透的影响做了灵敏性分析.     

An Analysis of Ripple and Error Fields Induced by a Blanket in the CFETR

The Chinese Fusion Engineering Tokamak Reactor(CFETR) is an important intermediate device between ITER and DEMO. The Water Cooled Ceramic Breeder(WCCB)blanket whose structural material is mainly made of Reduced Activation Ferritic/Martensitic(RAFM) steel, is one of the candidate conceptual blanket design. An analysis of ripple and error field induced by RAFM steel in WCCB is evaluated with the method of static magnetic analysis in the ANSYS code. Significant additional magnetic field is produced by blanket and it leads to an increased ripple field. Maximum ripple along the separatrix line reaches 0.53% which is higher than 0.5% of the acceptable design value. Simultaneously, one blanket module is taken out for heating purpose and the resulting error field is calculated to be seriously against the requirement.     

ITER中国氦冷固体实验包层模块温度场和氦气流场三维数值分析

采用通用计算流体力学软件Fluent对应用于国际热核实验堆(ITER)的实验包层模块(TBM)的第一壁Be、Be球床中子增殖区、Li4SiO4陶瓷球床氚增殖区、以及结构材料的温度场和氦气流道内流场进行了三维数值模拟,研究了TBM的温度场及冷却管道内的氦气流场的分布.结果表明,除极小区域外,材料的温度在该材料所允许的工作范围之内;氦气表现出很好的流动和换热特性.     

ITER中国液态锂铅实验包层模块氚提取系统设计

ITER中国液态锂铅实验包层模块氚提取系统(TES)是通过含0.1%H2的低压氦吹洗气流,在鼓泡器中将液态锂铅内产生的氚交换和载带出来,进入同位素分离系统连接进行氚提取.给出了该系统总体参数、工艺流程、辅助设施等设计.     

Electromagnetic analysis, structural integrity and progress on mechanical design of the ITER ferromagnetic insert

Ferromagnetic material is used to reduce the toroidal field ripple in JFT-2M [H. Kawashima, et al., Demonstration of ripple reduction by ferritic steel board insertion in JFT-2M, Nucl. Fusion, 41 (2001) 257-263] and JT-60U [H. Takenaga, the JT-60 Team, Overview of JT-60U results for development of steady-state advanced Tokamak scenario, Proceedings of the 21st IAEA Fusion Energy Conference, Chengdu, China, 2006]. In ITER, since the ferromagnetic material is inserted in the space between the double walls of ITER Vacuum Vessel (VV), it is called “ferromagnetic inserts”. Suitable material is selected to satisfy the design requirements of ITER. The proper location and amount of the ferromagnetic inserts are optimized with the goal of reduction of the toroidal field ripple. The ferromagnetic inserts are designed to minimize electromagnetic forces acting on them. The electromagnetic forces have been calculated with the latest disruption scenarios. Magnetization forces due to magnetic fields have also been calculated. Structural integrity has been validated by a structural analysis.