＂Tritium Well Depth＂ and ＂Tritium Well Time＂

Somewhat similar to, but quite different from the xenon-135 poisoning effects resulted from fission produced iodine-135 via β-decay during restart-up process of a fission reactor, a complete new concept of ＂tritium well depth and tritium well time＂ is first time introduced in fusion research area by authors. It shows the least required amount of tritium storage is to start up a fusion reactor ,and the least operating time for achieving the ＂tritium break even＂ during the initial start-up phase due to the finite tritium breeding time. The tritium well depth and tritium well time depend on the tritium recovery scheme and extraction process, the tritium retention of reactor components,     

Tritium Burn-up Depth and Tritium Break-Even Time

Similarly to but quite different from the xenon poisoning effects resulting from fission-produced iodine during the restart-up process of a fission reactor, we introduce a completely new concept of the tritium burn-up depth and tritium break-even time in the fusion energy research area. To show what the least required amount of tritium storage is used to start up a fusion reactor and how long a time the fusion reactor needs to be operated for achieving the tritium break-even during the initial start-up phase due to the finite tritium breeding time that is dependent on the tritium breeder, specific structure of breeding zone, layout of coolant flow pipe, tritium recovery scheme, extraction process, the tritium retention of reactor components, unrecoverable tritium fraction in breeder, leakage to the inertial gas container, and the natural decay etc., we describe this new phenomenon and answer this problem by setting up and by solving a set of equations, which express a dynamic subsystem model of the tritium inventory evolution in a fusion experimental breeder （FEB）. It is found that the tritium burn-up depth is 317g and the tritium break-even time is approximately 240 full power days for FEB designed detail configuration and it is also found that after one-year operation, the tritium storage reaches 1.18kg that is more than the least required amount of tritium storage to start up three of FEB-like fusion reactors.     

Microstructural evolution during containerless rapid solidification of Co-Si alloys

The Co-12%Si hypoeutectic, Co-12.52%Si eutectic and Co-13%Si hypereutectic alloys are rapidly solidified in a containerless environment in a drop tube. Undercoolings up to 207K (0.14T_E) are obtained, which play a dominant role in dendritic and eutectic growth. The coupled zone around Co-12.52%Si eutectic alloy has been calculated, which covers a composition range from 11.6 to 12.7%Si. A microstructural transition from lamellar eutectic to divorced eutectic occurs to Co-12.52%Si eutectic droplets with increasing undercooling. The lamellar eutectic structure of the Co-12.52%Si alloy consists of εCo and Co_3Si phases at small undercooling. The Co_3Si phase cannot decompose completely into εCo and αCo_2Si phases. As undercooling becomes larger, the Co_3Si phase grows very rapidly from the highly undercooled alloy melt to form a divorced eutectic. The structural morphology of the Co-12%Si alloy droplets transforms from εCo primary phase plus lamellar eutectic to anomalous eutectic, whereas the microstructure of Co-13%Si alloy droplets experiences a `dendritic to equiaxed' structural transition. No matter how large the undercooling is, the εCo solid solution is the primary nucleation phase. In the highly undercooled alloy melts, the growth of εCo and Co_3Si phases is controlled by solutal diffusion.     

Study on Chemical Behavior of Energetic Deuterium-implanted into Li2TiO3

In ITER test blanket module design, the elucidation of tritium recovery from solid tritium breeding material is one of critical issues and Li2TiO3 is a candidate of tritium breeding materials. In the present study, in order to understand tritium behavior in solid breeding material Li2TiO3, the X-ray photoelectron spectroscopy （XPS） and thermal desorption spectroscopy （TDS） experiments are carried out to elucidate the trapping behavior using 3 keV D2^＋ implanted sample. The Ti-2p XPS spectrum shows that a shoulder appeared at the lower energy side as increasing ion fluence, and it was suggested that Ti^3＋ was formed by the reduction of Ti^4＋.     

Activation Characteristics of Fuel Breeding Blanket Module in Fusion Driven Subcritical System

Shortage of energy resources and production of long-lived radioactivity wastes from fission reactors are among the main problems which will be faced in the world in the near future. The conceptual design of a fusion driven subcritical system (FDS) is underway in Institute of Plasma Physics, Chinese Academy of Sciences. There are alternative designs for multi-functional blanket modules of the FDS, such as fuel breeding blanket module (FBB) to produce fuels for fission reactors, tritium breeding blanket module to produce the fuel, i.e. tritium, for fusion reactor and waste transmutation blanket module to try to permanently dispose of long-lived radioactivity wastes from fission reactors, etc. Activation of the fuel breeding blanket of the fusion driven subcritical system (FDSFBB) by D-T fusion neutrons from the plasma and fission neutrons from the hybrid blanket are calculated and analysed under the neutron wall loading 0.5 MW/m2 and neutron fluence 15 MW.yr/m2. The neutron spectrum is calculated with the worldwide-used transport code MCNP/4C and activation calculations are carried out with the well known European inventory code FISPACT/99 with the latest released IAEA Fusion Evaluated Nuclear Data Library FENDL-2.0 and the ENDF/B-V uranium evaluated data. Induced radioactivities, dose rates and afterheats, etc, for different components of the FDS-FBB are compared and analysed.     

Rapid Hypoeutectic Growth Within a Highly Undercooled Liquid Under containerless Condition

Rapid hypoeutectic growth from a highly undercooled liquid was accomplished by containerless processing Ni-32% Sb hypoeutectic alloy in a 3m drop tube.The containerless state during the free fall of the droplet produces substantial undercooling up to 350K(0.24TL).The growth mechanism is found to transform from primary α Ni dendrite plus lamellar eutectic to lamellar eutectic and finally to anomalous eutectic if droplet undercooling exceeds the two thresholds of 112K and 242K,respectively.Based on the current eutectic and dendritic growth models,the eutectic coupled zone is calculated and used to explain the growth mechanism transition.Calculations also indicate that the growth of α-Ni primary dendrite was mainly controlled by solute diffusion.     

Effect of Low Diffusion Coefficient on Eutectic Instability of Al-25wt%Sm Alloy

Diffusion coefficient decides the solute diffusion length and is a critical parameter in the selection of microstructare scales and in governing microstructure transitions. Al-25 wt%Sm alloy is selected to reveal the impact of low diffusion coefficient on the eutectic instability, and the results are compared with those of Al-Cu alloys. Laser remelting experiments are performed and the transition growth velocity from euteetic to α-Al dendrite is examined. Compared with Al-Cu alloys, the eutectic instability takes place at a velocity more than one order of magnitude smaller. The theoretical calculation by the Trivedi-Magnin-Kurz （TMK） model also predicts that the eutectic will become instable at smaller growth velocity for Al-Sm alloy than Al-Cu alloy, which is ascribed to the low diffusion coefficient.     

300＃堆在线产氚回路及其应用

本文介绍了３００~＃堆在线产氚回路的组成及其主要指标、回路运行和释氚实验概况,阐明了在线产氚回路在聚变裂变混合堆包层产氚研究中的应用和前景． An in-pile tritium production apparatus in SPRR-300 and its main charactersare introduced. The operation of the apparatus and the tritium release experiments arebriefly described. The utilization of the apparatus in tritium production study of fusionfission hybrid reactor blanket and its future are reviewed.     

A Transition from Eutectic Growth to Dendritic Growth Induced by High Undercooling Conditions

Cu-8 wt.% A1 eutectic alloy was undercooled by up to 187K (0.14TE) using a drop tube technique. The crystal growth and phase selection mechanisms were investigated during containerless rapid solidification. It is found that the microstructural morphology is characterized by lamellar eutectic growth at small undercoolings. However, if the liquid alloy is undercooled by more than 25K, eutectic growth will be suppressed completely and the dendritic growth of (Cu) solid solution dominates its solidification process. When the undercooling exceeds 153 K, a microstructural transition from coarse dendrite to equiaxed dendrite takes place.     

Dynamic solidification mechanism of ternary Ag-Cu-Ge eutectic alloy under ultrasonic condition

The dynamic solidification of ternary Ag38.5Cu33.4Ge28.1 eutectic alloy within a 35 kHz ultrasonic field is investigated and compared with both its equilibrium solidification by DSC method and its rapid solidification in drop tube.The volume fractions of the primary(Ge) phase and pseudobinary(Ag+ε2) eutectic solidified within ultrasonic field are larger than those formed under equilibrium state,whereas that of ternary(Ag+ε2+Ge) eutectic exhibits the reverse trend.During rapid solidification,the liquid alloy droplet directly solidifies into ternary(Ag+ε2+Ge) eutectic if its diameter is smaller than 350 m.The ultrasound stimulates the nucleation of alloy melt and prevents the bulk undercooling.With the increase of sound intensity,the primary(Ge) phase transfers from faceted dendrites to nonfaceted blocks with blunt edges,and its grain size is remarkably reduced.Both pseudobinary(Ag+ε2) and ternary(Ag+ε2+Ge) eutectics experience a morphological transition from regular to anomalous structures.This indicates that their cooperative growth mode is replaced by independent growth of eutectic phases under the combined effects of cavitation and acoustic streaming.The ultrasound also shows a prominent coarsening effect to the pseudobinary(Ag+ε2) and ternary(Ag+ε2+Ge) eutectics.     

LiAlO_2陶瓷小球的堆外放氚行为

将LiAlO2陶瓷小球置于裂变反应堆中辐照,采用热解吸技术研究该类产氚材料的堆外放氚特性,考察了升温速率、载气组分、催化活性元素和提氚温度对氚释放行为的影响;采用电子自旋磁共振(ESR)实验技术研究了辐照缺陷的顺磁特征。结果表明:LiAlO2中氚的扩散速度慢,热解吸活化能高,氚释放主要分布在750~1000K;表面氢同位素交换反应贡献大,释氚形态受载气条件的影响较大,当氦气中添加H2时,会增大HTO转化成HT的比例;中子辐照会在LiAlO2中诱生F+,O-和O2-等缺陷色心,其退火湮灭行为与氚释放过程存在一定关系。     

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基于ITERCHHCSBTBM的设计特点,设计了相关的氚工艺辅助系统。描述了氚提取系统(TES)、冷却剂纯化系统(CPS)、氚测量系统(TMS)的功能、设计参数和工艺流程等。TES用于氚提取、储存、同位素的分离;CPS实现氧氮等杂质和氚的去除及冷却剂的定量处理和分析等功能;TMS不仅可以定量分析氚含量,而且必要时可替代TES。氚渗透及氚安全的分析表明,通过CHHCSBTBM以及辅助系统向环境释放的氚可控制在ITER的氚安全限度内。     

磁约束聚变堆次临界包层概念设计研究进展

为使磁约束聚变堆实现能量放大与氚自持,在其等离子体区周围设置次临界包层和产氚包层。采用天然铀合金燃料、轻水作冷却剂兼慢化剂,内嵌压力管式的次临界包层设计方案,通过对包层物理性能、结构概念设计、热工水力性能和安全分析,表明该方案可将聚变能量放大10倍以上,氚增殖比大于1.15,具有天然的临界安全性和良好余热安全性能。立足于近中期可利用的聚变技术,力争实现聚变能源的提前商用,为我国能源可持续发展提供一种有竞争力的技术选项。     

Z箍缩驱动聚变-裂变混合堆氚燃料循环系统氚盘存量与氚自持初步分析

为研究氚自持条件,建立了Z-FFR氚分析模型,基于理论方程和氚平均滞留时间方法进行计算,得到稳态运行时排灰气处理系统、氚增殖提取系统、同位素分离系统、水去氚化系统的氚质量流分别为52.30,25.40,81.30,3.60 g/day,对应的氚盘存量为52.30,25.40,8.13,1.80 g。同时以氚质量流推导出氚自持判断条件,分析了设计参数能够满足氚自持要求,同时获得了燃烧效率、氚增殖率、提取效率与氚自持的互补关系,三者作为关键参数相互依存,于临界值、设计值、理想值之间分析了氚的自持情况。     

基于运行反馈的压水堆氚排放量研究北大核心CSCD

以压水堆核电厂中氚的产生机理和氚源项计算模型为基础,结合对国内外大量压水堆核电厂的氚排放运行数据的系统性分析,识别出冷却剂硼酸活化和次级中子源活化是压水堆氚排放量的主要来源,其中对中国广核集团运行机组,锑铍中子活化后的产氚量对氚年排放量的贡献可达到40%,而氚从完整的锆合金包壳的燃料棒中的释放是可以忽略不计的。由于优化次级中子源是降低压水堆氚排放量的唯一有效措施,通过分析建议压水堆核电厂采用双层不锈钢包壳的次级中子源或者取消次级中子源以降低压水堆氚排放。     

球环型产氚聚变堆中子学分析

对球环型产氚聚变堆概念设计中的中子学设计进行了计算分析。此设计利用了球形环的先进等离子体物理性能和紧凑的结构特征,并尽量利用真空室内的空间安置氚生产包层以减少氚泄漏而提高氚增殖率,达到年产氚量1kg的目标。2D中子学计算得到的氚增殖率高于1．68的设计是其它类似设计没有达到的,进一步体现出球环型产氚聚变堆的先进性。     

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水冷陶瓷包层是中国聚变工程实验堆(CFETR)的三种候选包层概念之一。基于CFETR水冷陶瓷包层的一维中子学模型,通过蒙特卡罗输运模拟程序MCNP和活化计算程序FISPACT的耦合计算,经三维转换系数修正,分析了CFETR水冷陶瓷包层时间相关产氚特性。结果表明,当CFETR运行因子为0.5,聚变功率为200MW时,水冷陶瓷包层在运行5年、10年、20年后,氚增殖率(TBR)的降低都不显著,但是年产氚剩余量的降低很明显。此外,产氚包层内初始时刻TBR对产氚特性的影响也很大。     

CFETR 水冷陶瓷包层时间相关产氚特性初步分析

水冷陶瓷包层是中国聚变工程实验堆(CFETR)的三种候选包层概念之一。基于CFETR水冷陶瓷包层的一维中子学模型,通过蒙特卡罗输运模拟程序MCNP和活化计算程序FISPACT的耦合计算,经三维转换系数修正,分析了CFETR水冷陶瓷包层时间相关产氚特性。结果表明,当CFETR运行因子为0.5,聚变功率为200MW时,水冷陶瓷包层在运行5年、10年、20年后,氚增殖率(TBR)的降低都不显著,但是年产氚剩余量的降低很明显。此外,产氚包层内初始时刻TBR对产氚特性的影响也很大。     

氚在锆合金包壳材料中的扩散行为模拟

基于氚扩散基本模型建立了氚扩散行为一维模拟程序,对模拟程序进行了典型实验验证,模拟结果与实验结果符合较好。分析了不同氚浓度、温度分布对锆合金包壳材料中氚的扩散行为的影响。分析结果表明:包壳-芯块间隙内氚浓度的升高会导致进出包壳的氚扩散通量提高,渗透通量增大;由于包壳氧化层相对较低的扩散系数,包壳氧化层的存在对氚渗透有较大的限制作用;温度对氚扩散速率的影响很显著,温度越高,扩散速度越快;锆合金外表面氧化层的相对低温限制了氚渗透出包壳管的速率,温度梯度导致的热致扩散有利于氚向包壳冷测扩散。