聚变驱动次临界堆热中子上散射截面数据库开发及初步应用

为了提高水冷慢化聚变驱动次临界堆包层中子学分析的精度,在FDS团队自主研发的HENDL3.0/FG(Hybrid Evaluated Nuclear Data Library/Fine Group)细群核数据库基础上,本文采用国际通用应用核数据库加工程序NJOY,设计研发出考虑热中子上散射效应的截面核数据库。利用国际临界安全基准评价实验手册的例题对核数据库的精度进行了测试与校核,验证了数据的可靠性与正确性。同时,采用聚变驱动次临界的聚变裂变混合发电堆(FDS-EM)水冷慢化包层模型对核数据库进行了综合测试与分析,分别从理论及计算分析的角度预测与验证了热中子上散射效应对系统的有效增殖因数、氚增殖率、中子通量密度等参数的影响。     

不产生长寿命高放废物的先进核能系统

阐述了核废物分离－－嬗变（Ｐ－Ｔ）处置和先进核能系统（ＡＮＥＳ）和重要性及其物理基础，讨论了对化学分离的要求和现状，并对裂变堆、聚变－裂变混合堆、加速器驱动次临界堆等核废嬗变炉为主的３类先进核能系统作了简要讨论。最后，对我国开展核能系统研究的发展战略提出了建议。     

混合评价核数据库HENDL1.0的研制与基准检验

为满足聚变 裂变次临界混合堆设计和其他相关研究的需要 ,以世界几个主要基本评价核数据库为数据来源 ,通过优选建立了名为HENDL1 .0 /E的多用途核数据库 ,采用国际通行的核数据库处理程序系统NJOY和TRANSX等程序制作了相应的工作数据库 ,其中包括多能群输运截面库HENDL1 .0 /MG、连续能量点状输运截面库HENDL1 .0 /MC、燃耗数据库HENDL1 .0 /BU和响应函数库HENDL1 .0 /RF ,利用世界上流行的中子输运程序对已有的一系列基准检验实验进行模拟计算和比较分析以检验混合库HENDL1 .0的正确性和有效性。     

聚变驱动次临界堆双冷嬗变包层材料活化计算与分析

对聚变驱动次临界堆 (FDS Ⅰ )包层进行了材料活化计算与分析。利用多功能中子学程序系统VisualBUS1 .0及多群数据库HENDL1 .0 /MG进行中子输运计算 ,以获得包层各个功能区的中子注量率能谱 ;在此基础上 ,使用欧洲活化计算程序FISPACT及IAEA聚变活化数据库FENDL/A 2 .0分别对停堆初期包层不同功能区的剂量率水平和衰变余热水平、停堆后期结构材料与氚增殖剂 /冷却剂的活化性能及其杂质的控制要求进行了计算及分析。     

聚变驱动次临界堆双冷嬗变包层中子学设计与分析

对聚变驱动次临界堆的多功能双冷核废料嬗变包层进行了中子学设计和分析,设计目标是:①氚和钚燃料自持;②较少的初装料得到较高的废料嬗变率。使用的程序是自主开发的多功能中子输运/燃耗/优化程序VisuaIBUs1.0,相应的数据库是175群中子/42群光子的多群数据库HENDL1.0/MG。     

铅基反应堆研究现状与发展前景

以铅或铅合金(统称铅基材料)为冷却剂的反应堆具有良好的中子学、热工水力学和安全特性,已成为第四代先进核能系统、加速器驱动次临界核能系统(ADS)以及聚变堆的主要候选堆型之一。本文简要介绍了先进核能系统发展趋势和铅基反应堆在核能发展中的地位,重点对铅基反应堆的发展历史与现状、铅基反应堆的基本特性以及铅基反应堆未来的发展前景进行了总结。     

基于多维响应矩阵的中子能谱逆向调控方法及应用

中子能谱是影响核能系统安全性和经济性的重要参数,先进核能系统种类繁多,能谱差异大,准确的调控出先进核能系统的能谱对其发展有重要意义。本文利用基于响应矩阵的中子能谱逆向调控方法,以14MeV单能的聚变中子源为例,调控出聚变堆氚增殖包层、聚变裂变混合堆次临界包层、铅基快堆堆芯处的中子能谱,调控得到的中子能谱与目标能谱吻合较好,其中聚变堆氚增殖包层处的中子能谱与FNG上Mockup实验能谱比较,归一化能谱均方差降低了66%。对比结果表明本文方法能够实现多种类型先进核能系统中子能谱的精准调控。     

多用途核数据库HENDL2.0/MG/MC的重核临界基准校验

为适应聚变-裂变混合堆设计及其相关研究的需求制作混合多用途核数据库HENDL(Hybrid Evaluated Nuclear Data Library)的升级版本HENDL2.0.评价核数据来源主要选用美国公布的ENDF/B-Ⅶ.0库和国际原子能机构(IAEA/NDS)发布的聚变库FENDL-2.1.利用蒙特卡罗粒子输运程序MCNP以及FDS团队自主研发的大型集成多功能中子学计算与分析系统VisualBUS程序进行模拟计算,对已有的一些数据较为完备的基准实验例题进行基准测试和比较分析以检验混合库HENDL2.0的有效性和可信性.     

高放废物的嬗变处置与不产生长寿命高放废物的先进核能系统

高放废物的嬗变处置与不产生长寿命高放废物的先进核能系统李寿（中国原子能科学研究院）５各种装置的嬗变能力利用裂变堆、聚变堆、散裂源次临界装置嬗变长寿命核废物已有许多评价研究、中子学计算和实验、以及各种焚烧炉的概念设计。虽都还处于研究阶段，但对各种装置...     

高放废物嬗变研究发展及前景

高放废物的处置关系到核能的发展和环境保护。分离与嬗变作为高放废物处置的可能途径之一，在世界上已有近３０年的研究发展历史，目前，越来越受人们的关注。本文分别介绍了利用轻水堆、液态金属燃料堆、聚变堆（聚变－裂变混合堆）以及加速器驱动的次临界系统嬗变高放废物的原理、研究发展及前景。为我们开展高放废物嬗变研究提出一些建议。     

Georgia Tech Studies of Sub-Critical Advanced Burner Reactors with a D-T Fusion Tokamak Neutron Source for the Transmutation of Spent Nuclear Fuel

The possibility that a tokamak D-T fusion neutron source, based on ITER physics and technology, could be used to drive sub-critical, fast-spectrum nuclear reactors fueled with the transuranics (TRU) in spent nuclear fuel discharged from conventional nuclear reactors has been investigated at Georgia Tech in a series of studies which are summarized in this paper. It is found that sub-critical operation of such fast transmutation reactors is advantageous in allowing longer fuel residence time, hence greater TRU burnup between fuel reprocessing stages, and in allowing higher TRU loading without compromising safety, relative to what could be achieved in a similar critical transmutation reactor. The required plasma and fusion technology operating parameter range of the fusion neutron source is generally within the anticipated operational range of ITER. The implications of these results for fusion development policy, if they hold up under more extensive and detailed analysis, is that a D-T fusion tokamak neutron source for a sub-critical transmutation reactor, built on the basis of the ITER operating experience, could possibly be a logical next step after ITER on the path to fusion electrical power reactors. At the same time, such an application would allow fusion to contribute to meeting the nation’s energy needs at an earlier stage by helping to close the fission reactor nuclear fuel cycle.     

A Fusion Neutron Source Driven Sub-Critical Nuclear Energy System: A Way for Early Application of Fusion Technology

1. IntroductionAlthough the recent experiments and associatedtheoretical studies of fusion energy development havedemonstrated the feasibility of fusion power, it iscommonly realized that it needs hard work beforepure fusion energy could be commercially and eco-nomically utilized. On the other hand, the fissionnuclear industry has been falling on hard tithes re-cently since so far there has been no conclusion abouthow to deal with the long-lived wastes produced fromthe nuclear spent fuel and a…     

Suitability of Small Scale Linear Systems for a Fission–Fusion Reactor, Breeder, and Waste Transmutation

To date the magnetic fusion effort has been almost entirely devoted to only one application, that being a multi gigawatt central station electric plant. Given the already well established fission based industry, the likelihood that fusion will have any impact on curbing the current carbon-based energy demand in the 21st century is slim. This paper advocates that the first and primary use of fusion neutrons should be as the driver for a sub-critical fission nuclear energy system—a fission–fusion hybrid reactor. This system can also be utilized to transmute long-lived radioactive wastes, and breed fissile nuclear fuel for several additional fission reactors. A small-scale fusion system based on a reciprocating fusion cycle employing the magneto-kinetic compression of the Field Reversed Configuration (FRC) is particularly well suited for this application. The characteristics of this fusion neutron driver and the potential for transmutation of long-lived nuclear wastes and breeding of fissile nuclear fuel in a blanket are presented.     

次临界能源堆安全性研究

次临界能源堆由中心的托卡马克装置和围绕其的裂变包层组成。本文根据物理和热工专业分析计算得出的一种针对其裂变包层的燃料和冷却剂通道布置方式,分析设计的包层结构安全性和工程应用中的安全性。包层结构安全性分析使用CFD方法,计算了正常运行工况和冷却剂通道堵管的情况,得到堵管发生后包层的局部状况。通过RELAP程序模拟了裂变包层参与核电厂发电运行过程中,其本身所具有的固有安全性。本文通过计算发现了其安全上的薄弱环节,并提出了改进措施,为以后改进次临界能源堆安全性提供参考。     

Activation analysis and waste management for blanket materials of multi-functional experimental fusion–fission hybrid reactor (FDS-MFX)

The preliminary studies of the activation analysis and waste management for blanket materials of the multi-functional experimental fusion–fission hybrid reactor, i.e. Multi-Functional eXperimental Fusion Driven Subcritical system named FDS-MFX, were performed. The neutron flux of the FDS-MFX blanket was calculated using VisualBUS code and Hybrid Evaluated Nuclear Data Library (HENDL) developed by FDS Team. Based on these calculated neutron fluxes, the activation properties of blanket materials were analyzed by the induced radioactivity, the decay heat and the contact dose rate for different regions of the FDS-MFX blanket. The safety and environment assessment of fusion power (SEAFP) strategy, which was developed in Europe, was applied to FDS-MFX blanket for the management of activated materials. Accordingly, the classification and management strategy of activated materials after different cooling time were proposed for FDS-MFX blanket.     

The Spallator and APEX Nuclear Fuel Cycle a New Option for Nuclear Power

A new nuclear fuel cycle is described which provides a long term supply of nuclear fuel for the thermal LWR nuclear power reactors and eliminates the need for long-term storage of radioactive waste. Fissile fuel is produced by the Spallator which depends on the production of spallation neutrons by the interaction of high energy (1 to 2 GeV) protons on a heavy metal target. The neutrons are absorbed in a surrounding natural uranium or thorium blanket in which fissile Pu-239 or U-233 is produced. Advances in linear accelerator technology makes it possible to design and construct a high beam current continuous wave proton linac for production purposes. The target is similar to a sub-critical reactor and produces heat which is converted to electricity for supplying the linac. The Spallator is a self-sufficient fuel producer, which can compete with the fast breeder. The APEX fuel cycle depends on recycling the transuranics and long-lived fission products while extracting the stable and short-lived fission products when reprocessing the fuel. Transmutation and decay within the fuel cycle and decay of the short-lived fission products external to the fuel cycle eliminates the need for long-term geological age storage of fission product waste.     

Transmutation capabilities of the CERN Energy Amplifier System

Progress in particle accelerator technology makes it possible to use a proton accelerator to produce energy and to destroy nuclear waste efficiently. Energy Amplifier (EA) systems consist of a sub-critical fast neutron core driven by a proton accelerator. If well designed, they prevent any possible criticality accidents. It has been proposed to take advantage of this sub-criticality in order to use certain types of fuel with poor neutronic properties (for instance those with very small delayed neutron fractions). In this respect, they are particularly attractive for destroying, through fission, transuranic elements produced by present nuclear reactors. EA's could also transform efficiently and at minimal cost long-lived fission fragments using the concept of Adiabatic Resonance Crossing (ARC), an innovative method tested at CERN with the TARC experiment.     

聚变数据库系统FusionDB研发与应用

聚变研究和设计是一项需国内外广泛合作的系统工程,积累和共享数据是当前重要任务。为了更好地整合聚变数据,FDS团队设计和研发了集聚变数据和数据处理与分析软件于一体的聚变数据库系统FusionDB,系统涵盖了聚变堆设计与安全分析关键数据,是国际上首个包括核数据、材料数据、部件数据、聚变物理实验数据以及核计算仿真和可靠性与概率安全分析等功能的综合型聚变数据库系统。FusionDB已应用于国际热核聚变实验堆ITER、中国科学院FDS系列聚变堆概念设计与研究中。