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钍燃料
相关语句
  thorium fuel
     Status and development of the thorium fuel cycle
     钍燃料循环的现状和发展
短句来源
     The main difficulties in developing the thorium fuel cycle lie in the reprocessing and disposal of the waste and its economy, and the ways tried by foreign countries to solve the problems are presented in the paper.
     介绍了钍燃料循环在各种反应堆型中的应用,归纳了钍燃料循环的优势及其不足。 指出目前钍燃料循环发展中的主要困难是乏燃料的后处理及经济性问题,阐述了国外的后处理尝试方法。
短句来源
     The233Pa and 233U weight content in the thorium fuel in different power conditions is also examined. The results show that the power has effect on the macro section of the thorium fuel. When doing the core calculation with thorium fuel,the history-based local-parameters methodology is adopted.
     本文对不同定功率条件下,含全铀燃料和钍-铀燃料棒束的栅元截面参数随辐照值的变化以及钍燃料棒束中233Pa和233U的质量份额进行了计算分析,认为功率会对钍燃料的栅元宏观截面产生影响,在全堆计算中,栅元基本参数应尽量使用基于历史的局部参数法。
短句来源
     Compared with uranium fuel, thorium fuel manifests its characteristics in safety and economics.
     通过与铀燃料的对比,展示了含钍燃料在安全性和经济性上的特点。
短句来源
     Subchannel analysis of fuel channels that load fresh Thorium fuel and spent Thorium fuel in TACR are presented,based on the program COBRA. The similarities and differences of thermal hydraulics in TACR fuel channels between the two charging conditions are revealed.
     用COBRA程序对TACR中装载旧钍燃料和新钍燃料的燃料通道进行了子通道分析,揭示了TACR燃料通道在这两种堆芯装料情况下热工水力情况的异同。
短句来源
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  “钍燃料”译为未确定词的双语例句
     RESEARCH ON PHYSICAL PROPERTIES OF PWR CORE FOR MIXED FUEL (UO 2 +ThO 2)
     压水堆中使用均匀混合型铀-钍燃料(UO_2+ThO_2)的堆芯物理特性研究
短句来源
     Research on Physical Properties of Reactor Core in PWR Using Separated U-Th Fuel Assemblies
     压水堆中使用分立型铀、钍燃料组件的堆芯物理特性研究
短句来源
     The fuel cycle model is one of the most important problem in the concept design of Thorium Advanced CANDU Reactor(TACR).
     在钍基先进CANDU堆的概念设计中,钍燃料的循环利用方式是一重要问题。
短句来源
  相似匹配句对
     Status and development of the thorium fuel cycle
     燃料循环的现状和发展
短句来源
     The advantages and disadvantages of the thorium fuel cycle are given and the development of thorium fuel cycle in several types of reactors is introduced.
     概述燃料循环目前的发展状况。
短句来源
     Fuel cells
     燃料电池
短句来源
     Fuel Cell
     燃料电池
短句来源
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  thorium fuel
Utilization of the thorium fuel cycle promises uranium resource conservation and guarantees a long-term economic energy supply.
      
Furthermore addition of uranium to thorium fuel improved tritium production.
      
It is also necessary to efficiently close the thorium fuel cycle of fast breeder reactors by appropriate development of the fuel reprocessing and refabrication stages.
      
The Fast Breeder Test Reactor (FBTR) at Kalpakkam is expected to be an important tool for development of thorium fuel and fuel cycle technology.
      
A quick look at the economics of the thorium cycle for fast reactors, vis-a-vis the more conventional uranium cycle indicates only a small and acceptable cost disadvantage on account of the need for remote fabrication of recycled thorium fuel.
      
更多          
  th fuel
Dubna Cascade Code (version-2004) has been used for the Monte Carlo simulation of the 1500 MWt accelerator driven sub-critical system (ADS) with 233U + 232Th fuel using the IAEA benchmark.
      
A survey is given of the analysis of actinide nuclides by means ofa-spectrometry in high-level radioactivity process solutions resulting from reprocessing of spent U-Th fuel.
      
It decreased exponentially form the 1st to 10th fuel row.
      
For solid Th fuel reactors however molten salt technologies for reprocessing require a completely new R>amp;D program.
      
This means that reprocessing is an integral part of a sustainable Th fuel cycle.
      


A practical application of 232 Th in Qinshan 300 MW(e) PWR was searched by using separated U Th fuel assemblies and the Twin Refuelling system.From the calculation of ten cycles,it shows that if irradiation time of thorium assemblies in core of PWR is long enough (10 cycles),the amount of 233 U in core at the end of irradiation is increased to 212.6 kg and it could take part in the chain reaction of the core.In this way,the practical application of 232 Th could be reached.Compared...

A practical application of 232 Th in Qinshan 300 MW(e) PWR was searched by using separated U Th fuel assemblies and the Twin Refuelling system.From the calculation of ten cycles,it shows that if irradiation time of thorium assemblies in core of PWR is long enough (10 cycles),the amount of 233 U in core at the end of irradiation is increased to 212.6 kg and it could take part in the chain reaction of the core.In this way,the practical application of 232 Th could be reached.Compared with full uranium fuel assemblies,more than 200 kg 235 U could be saved for each cycle by using separaed U Th assemblies.It shows the prosperous future of Th U fuel cycle.Of course,there are still some engineering problems left to be solved for real application.

通过对分立型铀、钍燃料组件 ,使用在秦山 30 0MW电功率压水堆核电厂中堆芯物理特性的探讨 ,寻找2 3 2 Th在PWR中可能利用的途径。为此 ,特采用铀、钍燃料组件分立的双进料系统的装卸料方法 ,其堆芯寿期分别为铀组件 3个循环 ;钍组件 1 0个循环。并以秦山核电厂为参考电厂 ,进行了 1 0个循环的燃耗计算 ,每一循环装料时均有 4个钍组件进堆。计算结果表明 :到第 1 0循环寿期末 ,堆芯中 40个钍组件所含的2 3 3 U总量已达到 2 1 2 6kg ,可直接参与堆芯的链式反应 ,从而达到利用2 3 2 Th的目的。并可同全铀组件堆芯比较中看出 ,分立型铀、钍组件混装堆芯每一循环 (第 1 0循环后 )可少装 2 0 0多kg2 3 5U ,这样就为钍 铀燃料循环展示了光明的前景。当然如果要达到实际应用 ,仍有许多工程技术问题亟待解决

This paper presents the research of physics characteristics of all-SEU and Thorium-SEU CANFLEX fuel. Some important parameters (coolant void reactivity, burn-up and etc.) are calculated using the code WIMS-AECL. Compared with uranium fuel, thorium fuel manifests its characteristics in safety and economics. This paper also introduces how to select the parameters when using WIMS-AECL code.

对全铀CANFLEX燃料和含钍CANFLEX燃料的物理特性进行了研究。用WIMS-AECL程序计算了参考栅元的冷却剂空泡反应性、燃耗等参数。通过与铀燃料的对比,展示了含钍燃料在安全性和经济性上的特点。还特别介绍了WIMS-AECL程序在使用过程中的参数选择方法。

A perspective view of the thorium fuel cycle is provided in this paper. The advantages and disadvantages of the thorium fuel cycle are given and the development of thorium fuel cycle in several types of reactors is introduced. The main difficulties in developing the thorium fuel cycle lie in the reprocessing and disposal of the waste and its economy, and the ways tried by foreign countries to solve the problems are presented in the paper.

概述钍燃料循环目前的发展状况。介绍了钍燃料循环在各种反应堆型中的应用,归纳了钍燃料循环的优势及其不足。指出目前钍燃料循环发展中的主要困难是乏燃料的后处理及经济性问题,阐述了国外的后处理尝试方法。

 
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