The need and prospects for improved fusion reactors

Conceptual fusion reactor studies over the past 10–15 yr have projected systems that may be too large, complex, and costly to be of commercial interest. One main direction for improved fusion reactors points toward smaller, higher-power-density approaches. First-order economic issues (i.e., unit direct cost and cost of electricity) are used to support the need for more compact fusion reactors. The results of a number of recent conceptual designs of reversed-field pinch, spheromak, and tokamak fusion reactors are summarized as examples of more compact approaches. While a focus has been placed on increasing the fusion-power-core mass power density beyond the minimum economic threshold of 100–200 kWe/tonne, other means by which the overall attractiveness of fusion as a long-term energy source are also addressed.Nomenclature a Plasma minor radius at outboard equatorial plane (m) - A Plasma aspect ratioR _T /a - AC Annual charges ($/yr) - b Plasma minor radius in vertical direction (m) - B Magentic field at plasma or blanket (T) - B _c Magnetic field at the coil (T) - B Toroidal magnetic field (T) - B Poloidal magnetic field (T) - BOP Balance of plant - C Coil - COE Cost of electricity (mills/kWeh) - CRFPR Compact RFP reactor - CT Compact torus (FRC or spheromak) - c _FPC Unit cost of fusion power core ($/kg) - DC Direct cost ($) - DZP Dense Z-pinch - E Escalation rate (1/yr) - EDC Escalation during construction ($) - ET Elongated tokamak - F Annual fuel charges ($/yr) - FC Component of UDC not strongly dependent or FPC size ($/kWe) - FW First wall - FPC Fusion power core - f _Aux Fraction of gross electric power recirculated to BOP - f ₁ (IC+IDC+EDC)/DC - f ₂ (O&M + SCR + F)/AC - IC Indirect cost ($) - IDC Interest during construction ($) - I _w Neutron first-wall loading (MW/m²) - i Toroidal plasma current (MA) - j Plasma current density, I/a² - k _B Boltzmann constant, 1.602(10)^–16 (J/keV) - LWR Light-water (fission) reactor - MPD Mass power density 1000P_E/M_FPC (kWe/tonne) - M _N Blanket energy multiplication of 14.1-MeV neutron energy - M _FPC Mass of fusion power core (tonne) - n Plasma density (m^–3) or toroidal MHD mode number - O&M Annual operating and maintenance cost ($/yr) - p _f Plant availability factor - PFD Poloidal field dominated (CTs, RFP, DZP) - P Construction time (yr) - P_TH Thermal power (MWt) - P _E Net electric power (1-)P _ET (MWe) - P_ET Total gross electric power (MWe) - p_f Fusion power (MW) - q Tokamak safety factor (B /B _gq )(a/R _T ) - q _e EngineeringQ value, 1/e - R _T Major toroidal radius (m) - RFP Reversed-field pinch - RPE Reactor plant equipment (Account 22) - S Shield - SCR Annual spare component cost ($/yr) - SSR Second stability region for the tokamak - S/T/H Stellarator/torsatron/heliotron - ST Spherical tokamak or spherical torus - T Plasma temperature (keV) - TDC Total direct cost ($) - TOC Total overnight cost ($) - UDC Unit direct cost,TDC/10 ³ P _E ($/kWe) - V _p Plasma volume (m³) - W _p Plasma energy (GJ) - W _B Magnetic field energy (GJ) - Magnetic utilization efficiency, 2nk_BT/(B ²/2₀) - ₀ Permeability of free space, 4(10)^–7 H/m - XE Plasma confinement efficiency, a²/4_E - _e Plasma energy confinement time - _p Overall plant efficiency, _TH(1-) - _TH Thermal conversion efficiency - _FPC AverageFPC mass density (tonne/m³) - Plasma vertical elongation factor,b/a - Thickness of allFPC engineering structure surround plasma (m) - Total recirculating power fraction, (P _ET-P _E)/P _ET, or inverse aspect ratioa/R _T This work was performed under the auspices of USDOE, Office of Fusion Energy.     

取向硅钢热轧卷形不良原因分析与改进

取向硅钢卷形质量直接关系到成材率,针对某钢厂生产取向硅钢热轧基料卷取尾部滑移,分析了产生的主要原因,通过对夹送辊辊缝标定、侧导板位置测量、辊道滞后率调整、精轧轧制中心线调整等措施,取向硅钢的尾部卷形大有提升。     

基于模拟分析技术和随机搜索算法的化工过程能量集成方法研究

夹点和模拟分析技术已在化工能量集成中广泛应用.今以夹点技术为基础,对化工过程系统用能进行诊断,根据"过程用能一致性"原则提出能量集成改造方案,通过改变塔压实现塔顶冷凝器与塔底再沸器的热集成多效蒸馏.夹点技术实现的优化目标仅是热回收最大或公用工程能耗最小,不能实现包括设备整体费用最小的过程全局最优化.研究基于模拟技术,通过灵敏度分析,得到精馏塔各操作参数的样本映射数据,通过多项式拟合得到参数关联方程,并在遗传算法及模式搜索中设计过程费用函数,提出了将模拟分析技术与随机搜索算法相结合的,以过程费用函数最小化为优化目标的能量集成方法.工业实例的成功设计应用证明了其有效性和可行性.     

无分流换热网络合成和控制的集成研究

提出了无分流换热网络合成和控制集成的策略和方法、步骤,建立了合成和控制同步优化的数学模型,使得换热网络的合成和控制的集成研究从试探法向数学规划方法发展,从理论研究向实用性方向发展,实现了同时考虑控制要求的换热网络的自动合成。通过示例说明了本文所提方法的有效性和实用前景。     

马钢CSP卷取机夹送辊控制的优化措施

针对马钢CSP热轧卷取夹送辊的缠辊故障,提出相应的优化改造措施。     

运用夹点设计法对一实际换热网络的改造

随着能源价格的不断提升,化工企业的节能降耗成为紧迫必行的任务。通过在对一实际过程的换热网络结构分析的基础上提取热、冷工艺物流,在给定的最小传热温差（20℃）限制下运用夹点设计法合成具有最大热回收的新换热网络;采用断开热负荷回路、取消热负荷较小的换热器达到减少换热器个数、简化网络的目的;由于热负荷转移造成了某些换热器传热温差违反最小传热温差限制、甚至出现传热温差为负值（违反热力学第二定律）的情况,采用能量松弛法恢复这些换热器的传热温差至给定的最小传热温差。经过调优后换热器网络总换热设备个数与原实际网络的相同,但与原实际网络相比,热、冷公用工程均节省1220kW。     

The Rayleigh-Taylor instability in the spherical pinch

The spherical pinch (SP) concept is an outgrowth of the inertial confinement model (ICF). Unlike the ICF, where instabilities, especially the Rayleigh-Taylor instability, have been studied extensively, the instability study of the spherical pinch has just begun. The Rayleigh-Taylor instability is investigated for the first time in the SP in the present work. By using the simple condition for the Rayleigh-Taylor instability p·<0 (density and pressure gradients have opposite direction), we have qualitatively identified the regions for development of instabilities in the SP. It is found that the explosion phase (central discharge) is stable and instabilities take place in the imploding phase. However, the growth rate for the instability is not in exponential form, and the appearance of the Rayleigh-Taylor instability does not prevent the main shock wave from converging to the center of the sphere.     

基于ProE的捏花刀盘设计及运动仿真

捏花刀盘是捏花机的主要部件之一,主要功能是实现切断面皮及成形食品花皱．利用ProE参数化特征造型技术,创建了捏花刀盘i维模型,实现捏花刀盘组快速装配及运动仿真,从而提高了设计质量,缩短了开发周期．     

夹点技术在润滑油加氢脱酸装置节能改造中的应用

针对润滑油加氢脱酸处理装置,对装置流程进行了模拟,分析了现有换热网络,发现了两处违背夹点匹配原则的换热,并根据夹点技术设计原则提出了改造方案。在该方案中充分利用反应生成油和热高分气高温位热源,提高了热能回收率,加热负荷降低了61.8%,冷却负荷降低了84.5%,得到了良好的效果和可观的经济效益。     

啤酒生产用能改造方案的调优分析

采用夹点分析法对某啤酒厂间歇生产过程的糖化工序进行用能分析,指出了目前糖化工序存在的一些用能不合理的问题。通过对直接热集成、带中间热贮存的热集成和带热泵的热集成等不同改造方案的分析比较,提出了节能改造优选方案,并对热泵的应用及限制进行了探讨,为啤酒厂节能改造与工程设计提供了可靠的依据。