增殖堆

为满足下世纪上半叶核能迅速发展的需要，设计了为轻水堆提供充足核燃料的磁镜聚变增殖堆CHD。

A mirror fusion breeder , CHD , has been designed for providing plenty of nuclear fuel for light water reactors to meet the needs for rapid development of nuclear power in the first half of next century .

磁镜聚变增殖堆概念设计初步报告

Conceptual design study for a mirror fusion breeder

聚变增殖堆液态金属Li自冷包层的热工水力分析

Thermal hydraulic analyses of liquid lithium self-cooled blanket for a fusion breeder

Th-~（233）U热中子增殖堆某些物理特性的探讨

Some physical properties of the Th - ~ ( 223 ) U thermal-neutron breeder reactor

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数控双环直流可逆调速系统阶跃扰动动态速降分析

MHD Pressure Drop Analysis for a Lithium Cooled Blanket of Tokamak Engineering Test Breeder Step forced Dynamic Speed Drop Analysis Digital Control , Dual Ring , Direct Current and Reversible Speed Governing System

MOX燃料在国外已成功应用于轻水堆和快中子增殖堆中。

The MOX fuel has been successfully applicated in the LWRs and FBRs .

介绍了核工业西南物理研究院聚变实验增殖堆工程概要设计（FEB-E）中的氚系统设计研究。

A summary of the tritium system design studies for the engineering outline design of a fusion experimental breeder ( FEB-E ) is presented .

对国家863项目聚变实验增殖堆工程概要设计（FEB-E）进行了氚环境安全问题评估。

The tritium environmental contamination issues are evaluated for the engineering outline design of the Fusion Experimental Breeder ( FEB-E ) which has been supported by the 863-high-tech - project in China .

运用零维模型评估了流动液态锂幕帘作为聚变实验增殖堆工程概要设计（FEB-E）第一壁对聚变等离子体的影响。得到了锂液帘工作温度对堆芯有效平均等离子体电荷？

A global model assessments of the effects of a flowing lithium curtain on plasma has been performed , which is utilized as the first wall for the engineering outline design of the Fusion Experimental Breeder ( FEB-E ) .

钠冷快增殖堆池式钠火事故分析计算

Analysis and Calculation of the Pool Sodium Fire Accident of LMFBR

池式快增殖堆主容器的动力特性研究

Dynamic characteristics study for main vessel of pool-type fast breeder reactor

加速器驱动的次临界快增殖堆中子学研究

Neutronics Study of Accelerator driven Sub critical Fast Breeding Reactor

铅冷快增殖堆物理和热工水力研究

Physical and thermohydraulic study on lead cooled fast breeder reactor

核能发展途径与快增殖堆在核能中的地位

Ways for the Nuclear Energy DeveloPment & Position of FBR in the Nuclear Energy

聚变增殖堆的中子学设计

Neutronics design for a fusion breeder

随着我国核电技术的发展，自主研制钠冷快中子增殖堆十分必要。

Along with the development of nuclear power technology in china , it is necessary to develop the fast breeder reactor ( fast reactor ) through own efforts .

增殖堆能满足10个以上同等规模功率轻水堆的核燃料的需要，它可以在不需要进行再处理的情况下直接加浓燃料。

The breeder is able to support the nuclear fuel needs for more than 10 LWRs of equal scale in power with fuel enriched directly in CHD without reprocessing .

本文第一部份简要说明第一代核电站堆型发展的局限性和发展快中子增殖堆的必要性。

The first part of this paper describes briefly the limitation of the development of the first generation reactors for nuclear electricity and the necessity of the development of fast breeder reactors .

快中子增殖堆核燃料的增产速度很高，但初装的可裂变材料多，基建投资大，其初始发展阶段所需燃料向须由热中子转化堆提供。

Although the gain of nuclear fuel for FBR is very fast , more inventory of fissible fuel and higher capital cost are needed , and the inventory during initial stage of FBR development must be supplied by the thermal converters .