高功率密度包层的热结构力学分析与优化

以混合堆FEB(FusionExperimentalBreeder)的堆芯参数和真空室尺寸为设计基准,高功率密度包层是用作嬗变核废物的。在高功率密度包层的工程设计阶段,进行了包层的热结构力学(Thermomechanics)分析与优化。包层模件采用Pro/ENGINEER2000i2设计制图编码建立模型后,随即转入Pro/MECHANICA2000i2功能编码进行热结构力学分析,即稳态热分析和稳态热应力分析。在分析期间,依据传热学和材料力学,减小包层表面热负载系的分布起伏,优化氦冷却管板屏的拱弧曲率、圆角、以及其与氦汇流腔的先进焊接工艺等。设计优化后,最终的分析计算表明:采用HT9铁素体钢制作的包层冷却屏构件的最高温度为350℃,最大剪应力≤80MPa。包层运行将具有良好的热结构力学安全裕度。     

CFETR COOL包层热-机械性能研究

超临界二氧化碳(sCO₂)液态锂铅包层(COOL)是中国聚变工程实验堆(CFETR)的候选包层，其主要功能是增殖产氚、屏蔽中子辐射以及能量转换发电。COOL包层在正常运行工况下需要承受冷却剂压力、热应力、重力、电磁力等载荷。本文在不考虑重力和电磁载荷的情况下，采用ANSYS有限元方法对COOL包层扇段的赤道面外包层模块进行热-机械性能分析，结果表明，COOL包层在正常运行工况下，各类材料的最高温度不超过限值，并且结构应力能够满足ITER SDC-IC设计标准，分析结果可为包层优化设计提供重要参考和数据支撑。     

聚变堆固态产氚包层中子学优化方法研究与应用

为提升聚变堆包层产氚性能,更好地满足氚自持要求,首先,基于中子微扰理论与模拟退火算法开发了适用于聚变堆产氚包层（TBB）中子学优化新算法与新程序。其次,选取中国聚变工程实验堆（CFETR）氦冷固态包层,完成了全堆中子学性能优化的示范性应用。最后,对优化后的包层方案进行了热工、流体、结构的三维有限元校核。结果表明：(1)相比于传统包层中子学优化算法,本文所提出的优化算法具有更好的优化效果与更高的优化效率;(2)本文所开发的智能优化程序可更好地满足聚变堆TBB中子学优化与设计的需求,可为包层设计提供算法理论基础与程序支撑。     

聚变-裂变混合堆次临界能源包层结构的热-力耦合分析

探讨了一种新型聚变-裂变混合堆次临界能源包层的有限元建模方法。应用ANSYS Workbench软件建立了该次临界能源包层的3D结构模型,并对该模型进行了稳态热分析、热-力耦合分析,获得了包层各零件的应力分布及变形分布,分析了包层各零件的强度、刚度,利用热-力耦合分析找到了该次临界能源包层的薄弱环节。计算结果表明,该包层满足强度、刚度要求,为该次临界能源包层的设计和改进提供了理论依据。     

超临界水冷固态实验包层中子学与热工水力特性研究

基于国际热核聚变实验堆(ITER)实验包层方案,提出了一个超临界水冷固态实验包层概念设计方案。设计采用Be作为中子倍增剂,Li4SiO4作为氚增殖剂,CLAM钢作为结构材料。包层第一壁采用多层盘道设计以提高第一壁出口温度,内部采用增殖剂与中子倍增剂分层布置以提高热沉积与氚增殖率。为验证包层设计的可行性,分析计算了三维包层氚增殖率与热沉积的分布,然后根据中子学计算得到的结果对超临界水冷固态实验包层进行了数值模拟研究。结果表明:包层功率密度分布较合理;氚增殖率满足运行中氚自持的要求;在冷却剂出口温度达到500℃条件下材料温度不超过限值。该设计方案能满足中子学设计与热工水力的要求。     

托卡马克工程试验增殖堆Li冷包层的磁流体动力学压降分析

本文对液态金属 Li 流过托卡马克工程试验增殖堆自冷包层的磁流体动力学(MHD)压降进行了分析,讨论了内侧包层有无裂变、燃料元件的形式、包层能量倍增因子 M 及第一壁冷却孔道宽度对包层总压降的影响,从 MHD 流动分析的观点,为中子学、结构和热工水力设计提出了设计要求。     

CLAM钢基体上大气等离子体喷涂制备氧化铝涂层工艺研究

液态金属锂铅包层是目前国际上聚变堆包层设计研究的主流方案之一,但其仍面临高氚渗透率、液态锂铅对包层结构材料的腐蚀以及锂铅流动引起的磁流体动力学MHD效应等问题,而包层结构材料表面加覆涂层是解决上述问题的关键技术之一。本实验尝试利用大气等离子体喷涂(APS)工艺在中国低活化马氏体CLAM钢上制备多功能氧化铝涂层,试验结果表明:涂层与基底具有较好的结合强度,平均值为31.7 MPa;涂层电阻率为5.26×109~1.54×1010Ω.m;并呈现较高的显微硬度和致密度。本工作可为未来聚变堆液态锂铅包层涂层制备提供理论依据和技术储备。     

加速器驱动快-热包层耦合次临界系统的性能研究

通过研究表明:加速器驱动快-热包层耦合次临界系统(ADFTS)具有同时高效嬗变锕系元素(MA)和裂变产物(FP)的优点.从中子物理学角度,对ADFTS的能量放大行为进行了分析,提出了快包层中子放大系数和快-热包层中子耦合系数的概念,并给出了中子放大系数的计算方法.对加速器驱动次临界系统的增殖能力进行了研究.研究表明,ADS具有比常规临界反应堆更高的增殖能力.     

托卡马克工程试验堆包层结构应力分析

本文给出了托卡马克工程试验堆包层结构没计的主要特点和包层设计的主要参数。利用线弹性结构分析程序SAP_(5P)和SAP_6程序对包层结构进行应力分析。考虑了包层燃料球重量、温度载荷和冷却剂压力载荷。计算结果表明,在现行设计参数条件下,包层材料应力在所选材料的许用应力范围内,包层结构设计是基本可行的。     

中国聚变工程试验堆包层的核热耦合效应研究

本文以中国聚变工程试验堆（CFETR）的氦冷固态包层和水冷固态包层为研究对象,基于蒙特卡罗程序MCNP和计算流体力学程序FLUENT,利用3D-1D-2D耦合方法和伪材料方法,分别对200 MW的氦冷固态包层和水冷固态包层及1.5 GW的水冷固态包层方案进行了核热耦合计算分析。研究结果表明,金属铍的热散射效应和轻水密度是聚变包层核热耦合效应的主要来源,核热耦合效应对氦冷固态包层的影响可忽略,对水冷固态包层的氚增殖比和温度分布有一定程度的影响。     

Design optimization of first wall and breeder unit module size for the Indian HCCB blanket module

The Indian test blanket module(TBM) program in ITER is one of the major steps in the Indian fusion reactor program for carrying out the RD activities in the critical areas like design of tritium breeding blankets relevant to future Indian fusion devices(ITER relevant and DEMO).The Indian Lead–Lithium Cooled Ceramic Breeder(LLCB) blanket concept is one of the Indian DEMO relevant TBM,to be tested in ITER as a part of the TBM program.Helium-Cooled Ceramic Breeder(HCCB) is an alternative blanket concept that consists of lithium titanate(Li_2TiO_3) as ceramic breeder(CB) material in the form of packed pebble beds and beryllium as the neutron multiplier.Specifically,attentions are given to the optimization of first wall coolant channel design and size of breeder unit module considering coolant pressure and thermal loads for the proposed Indian HCCB blanket based on ITER relevant TBM and loading conditions.These analyses will help proceeding further in designing blankets for loads relevant to the future fusion device.     

Liquid metal magnetohydrodynamic flows in manifolds of dual coolant lead lithium blankets

An attractive blanket concept for a fusion reactor is the dual coolant lead lithium (DCLL) blanket where reduced activation steel is used as structural material and a lead lithium alloy serves both to produce tritium and to remove the heat in the breeder zone. Helium is employed to cool the first wall and the blanket structure.Some critical issues for the feasibility of this blanket concept are related to complex induced electric currents and 3D magnetohydrodynamic (MHD) phenomena that occur in distributing and collecting liquid metal manifolds. They can result in large pressure drop and undesirable flow imbalance in parallel poloidal ducts forming blanket modules.In the present paper liquid metal MHD flows are studied for different design options of a DCLL blanket manifold with the aim of identifying possible sources of flow imbalance and to predict velocity and pressure distributions.     

Overview of Helium Cooled Ceramic Reflector Test Blanket Module development in Korea

Korea plans to install and test Helium Cooled Ceramic Reflector (HCCR) Test Blanket Module (TBM) in the ITER, because the HCCR blanket concept is one of options of the DEMO blanket. Currently, many design and R&D activities have been performed to develop the Korean HCCR TBM. An integrated design tool for a fusion breeder blanket has been developed based on nuclear technologies including a safety analysis for obtaining a license for testing in the ITER. A half-scale sub-module mockup of the first wall with the manifold was fabricated, and the manufacturability and thermo-hydraulic performances were evaluated. High heat load and helium cooling test facilities have been constructed. Next, the recent status of TBM material development in Korea was introduced including Reduced Activation Ferritic Martensitic (RAFM) steel, lithium ceramic pebbles and silicon carbide (SiC) coated graphite pebbles. Several fabrication methods of RAFM steel, lithium ceramic pebbles, and silicon carbide coating on graphite pebbles were investigated. Recent design and R&D progress on these areas are introduced here.     

聚变增殖堆液态金属Li自冷包层的热工水力分析

完成了托卡马克商用混合堆 TCB(Tokamak Commercial Breeder)Li 自冷包层设计的热工水力分析,讨论了热工水力设计中的一些关键问题。用两维有限元热传导程序 AYER 计算了 TCB 包层的温度分布,用液态金属 MHD(Magnetohydraudynamic)压降公式计算了包层的压降。同时,还分析了包层冷却剂丧失事故 LOCA 的瞬态热工过程。分析表明,正常工况下,包层结构材料最高温度,结构材料与冷却剂界面最高温度,以及包层总压降都满足堆设计要求。在 LOCA 工况下,如果停堆后1小时内包层中的燃料球能够借助重力卸出包层,第一壁和包层是安全的,并且不会受到损伤。     

聚变制氢堆高温液态包层热工水力学新概念研究

在深入分析聚变堆包层设计要求和目前技术发展水平的基础上,根据热化学工艺制氢需要高温热的要求,提出了一个基于技术相对成熟的低活化铁素体/马氏体钢作为主要结构材料、高压氦气与液态LiPb合金作为冷却剂、具有创新性“多层流道插件”结构方案以获得高温热能的包层热工水力学概念,建立了热工水力学模型,在利用有限元数值模拟程序进行模拟计算的基础上分析了这种新概念包层的可行性。     

Structural analysis and optimization for ITER upper ELM coil

ITER ELM coils are used to mitigate or suppress Edge Localized Modes (ELM), which are located between the vacuum vessel (VV) and shielding blanket modules and subject to high radiation levels, high temperature and high magnetic field. These coils shall have high heat transfer performance to avoid high thermal stress, sufficient strength and excellent fatigue to transport and bear the alternating electromagnetic force due to the combination of the high magnetic field and the AC current in the coil. Therefore these coils should be designed and analyzed to confirm the temperature distribution, strength and fatigue performance in the case of conservative assumption. To verify the design structural feasibility of the upper ELM coil under EM and thermal loads, thermal, static and fatigue structural analysis have been performed in detail using ANSYS. In addition, design optimization has been done to enhance the structural performance of the upper ELM coil.     

ITER中国液态锂铅实验包层模块结构热应力数值模拟

使用有限元程序对中国向国际热核实验堆ITER实验包层工作组提交的双功能锂铅实验包层模块(DFLL-TBM)的两种结构设计方案即双冷LiPb包层DLL和单冷准静态LiPb包层SLL进行热应力数值模拟,在包层结构设计、热工水力学设计和中子学计算基础上,给出包层结构温度场和应力场分布,依据ITER高温结构设计标准,进一步对包层高温部件进行力学性能分析.根据这些模拟结果,分析两种结构基本设计方案的合理性和可行性,并作为进一步优化分析的基础.     

Nuclear Characteristics of D-D Fusion Reactor Blanket, (II)

The nuclear characteristics of the thermal blanket and blanket-shield designs are analyzed to provide a basis for optimizing the blanket design of D-D fusion reactors. The thermal blanket is devised to yield high energy deposition in a compact blanket through the use of neutron multiplier and energy converter with 1/v neutron absorption cross section. The blanket-shield design, on the other hand, aims at providing acceptably good shielding characteristics to protect the superconducting magnet by incorporating shielding substances within the blanket itself.

The results of calculation reveal that the thermal blanket design provides only modest energy deposition in the blanket despite its use of beryllium, which is limited in availability. In contrast, the blanket-shield concept is found to offer attractive possibilities in terms of nuclear characteristics, and the results of this analysis point toward the blanket-shield concept as the logical choice for D-D fusion reactor blankets.     

Design development and analytical assessment of LLCB TBM in Russian Federation during 2012–2013

The activity on the design, analysis, and R&D for the test blanket module (TBM) with lead–lithium (LL) eutectic coolant and ceramic breeder (CB) was performed in the Russian Federation (RF) according to the technical program of cooperation between the leading research institutes of India (“leader” of the LLCB TBM concept) and RF (“partner”). During the period of 2012–2013, the joint efforts of the RF and Indian specialists were focused on the development of the TBM's basic design with an optimal set of parameters (in particular for testing on both H-H and H-D operation phases of International Thermonuclear Experimental Reactor (ITER) machine). This article briefly describes the results of the TBM design and analysis that have been obtained by the RF specialists (“NIKIET” and D.V. Efremov Institute) in support of the LLCB concept (both DEMO blanket and TBM itself). The main directions of this activity in RF institutes were as follows:

• –development of the TBM design taking into account the ability to manufacture the TBM elements (load-bearing casing, tritium-breeding zone, and attachment system);
• –thermal analysis (in both stationary and transient approaches) of TBM design options (four variations of helium and eutectic flowing directions);
• –structural analysis of TBM design elements for Inductive I operation mode; and
• –recommendations (based upon the results of comparative analysis) on the reference design to be used on further stages of concept development.

The critical issues and further plans on the development of LLCB TBM and corresponding DEMO blanket in the RF are also presented in this article.