...
首页> 外文期刊>Journal of nuclear science and technology >Fast Reactor Fuel Reprocessing Technology in India
【24h】

Fast Reactor Fuel Reprocessing Technology in India

机译:印度快速反应堆燃料后处理技术

获取原文
获取原文并翻译 | 示例

摘要

The limited indigenous uranium resource coupled with the need of energy independence necessitated the Department of Atomic Energy (DAE) in India to opt for a three-stage nuclear power program comprising of PHWRs in Stage 1, FBRs in Stage 2 and Th-U~(233) based reactors in Stage 3, respectively to meet the energy needs of the growing Indian economy. Presently the country has stepped into the 2nd Stage. The transition from the Stage 1 to 2 was fruitful thanks to the 2-decade long R&D experience gained in Fast Reactor Fuel Reprocessing (FRFR). Closing the fast reactor fuel cycle through FRFR was inevitable for the success of the Indian Nuclear Power Program (INPP). The latest achievement by the center was the successful reprocessing of 100 GWd/t burnup mixed carbide fuel with 70% Pu, discharged from the Fast Breeder Test Reactor (FBTR) which is also located in the same center. The designs of the various equipments and process flow sheet had stemmed from the above experiences thereby increasing the confidence level in the future plans of the Department. In this paper, an overview of the experiences in FRFR with glimpses of the various developmental activities towards the future plants is spelt out.
机译:本地铀资源有限,加上需要能源独立性,印度原子能部(DAE)不得不选择三阶段核电计划,该计划包括第一阶段的PHWR,第二阶段的FBR和Th-U〜( 233)的反应堆分别位于第3阶段,以满足不断增长的印度经济的能源需求。目前,该国已进入第二阶段。由于在快速反应堆燃料后处理(FRFR)中获得了长达20年的研发经验,从第一阶段到第二阶段的过渡非常有成果。通过FRFR结束快速反应堆燃料循环对于印度核电计划(INPP)的成功是不可避免的。该中心的最新成就是成功地处理了100 GWd / t燃耗为70%Pu的混合碳化物燃料,该燃料由位于同一中心的快速繁育试验堆(FBTR)排出。各种设备和工艺流程图的设计源于上述经验,从而提高了该部未来计划的信心水平。本文阐述了FRFR的经验概述,并简要介绍了对未来植物的各种开发活动。

著录项

相似文献

  • 外文文献
  • 中文文献
  • 专利
获取原文

客服邮箱:kefu@zhangqiaokeyan.com

京公网安备:11010802029741号 ICP备案号:京ICP备15016152号-6 六维联合信息科技 (北京) 有限公司©版权所有
  • 客服微信

  • 服务号