...
  • 主题
高级搜索  >
历史搜索 清空历史
首页> 外文期刊>Nuclear Technology >MINOR ACTINIDE-BEARING OXIDE FUEL CORE DESIGN STUDY FOR THE JSFR
【24h】

MINOR ACTINIDE-BEARING OXIDE FUEL CORE DESIGN STUDY FOR THE JSFR

机译：JSFR含亚胺氧化物燃料核心设计研究

获取原文
获取原文并翻译 | 示例
           
页面导航
  • 摘要
  • 著录项
  • 相似文献
  • 相关主题

摘要

In the Fast Reactor Cycle Technology Development (FaCT) project, a sodium-cooled fast reactor (SFR) with mixed-oxide (MOX)fuel and an SFR with metal fuel were selected as the primary and the secondary candidates, respectively, for the Japan Sodium-Cooled Fast Reactor (JSFR). The present study focuses on the effects of transuranium (TRU) composition in the design for the JSFR core with MOXfuel. In the transitional stage from light water reactor (LWR) to fast breeder reactor (FBR), there is the possibility for FBR fuel to have high minor actinide (MA) content due to the recycling of LWR spent fuel. High MA content affects core and fuel designs as follows: the neutronic reactivity characteristic changes; the linear power limit is reduced because of decreases of thernmelting point and thermal conductivity in the fuel; the gas plenum length is extended because of an increase in He gas generation. Thus, to evaluate the effects quantitatively, design studies for cores with two TRU compositions were conducted: an FBR multirecycle composition with ～ 1 wt% (in heavy metal) of MA content and an LWR recycle composition for which 3 wt% of MA content was assumed as a tentative target. The results show that the change from the FBR multirecycle composition to the LWR recycle composition leads to a sodium void reactivity increase of 10%, a linear power limit decrease of 1 to 2%, and a gas plenum length increase of 5%. As a result, the effects of TRU composition on the core and fuel designs were revealed to be benign.
机译：在快速反应堆循环技术开发（FaCT）项目中，日本分别选择了混合氧化物（MOX）燃料的钠冷快堆（SFR）和金属燃料的SFR作为主要候选对象和次要候选对象。钠冷快堆（JSFR）。本研究着重于含MOXfuel的JSFR堆芯设计中的铀（TRU）组成的影响。在从轻水反应堆（LWR）到快中子增殖堆（FBR）的过渡阶段，由于LWR乏燃料的再循环，FBR燃料可能具有较高的次minor系元素（MA）含量。高MA含量会影响堆芯和燃料设计，如下所示：中子反应性特征发生变化；由于燃料的熔点和热导率的降低，降低了线性功率极限。由于氦气生成量的增加，气室长度延长。因此，为了定量评估效果，针对具有两种TRU组成的岩心进行了设计研究：一种FBR多循环组合物，其MA含量约为1 wt％（重金属），一种LWR循环组合物，其MA含量为3 wt％。假定为暂定目标。结果表明，从FBR多循环组成到LWR循环组成的变化导致钠空隙反应性增加10％，线性功率极限减少1-2％，气室长度增加5％。结果，显示出TRU组成对堆芯和燃料设计的影响是良性的。

著录项

  • 来源
    《Nuclear Technology》 |2010年第1期|170-180|共11页
  • 作者

    MASAYUKI NAGANUMA; TAKASHI OGAWA; SHIGEO OHKI; TOMOYASU MIZUNO; SHOJI KOTAKE;

  • 作者单位

    Japan Atomic Energy Agency, 4002 Narita-cho, Oarai-machi, Higashi-ibaraki-gun, Ibaraki 311-1393, Japan;

    Japan Atomic Energy Agency, 4002 Narita-cho, Oarai-machi, Higashi-ibaraki-gun, Ibaraki 311-1393, Japan;

    Japan Atomic Energy Agency, 4002 Narita-cho, Oarai-machi, Higashi-ibaraki-gun, Ibaraki 311-1393, Japan;

    Japan Atomic Energy Agency, 4002 Narita-cho, Oarai-machi, Higashi-ibaraki-gun, Ibaraki 311-1393, Japan;

    Japan Atomic Power Company, 1-1 Kanda-Mitoshiro, Chiyoda-ku, Tokyo 101-0053, Japan;

  • 收录信息 美国《科学引文索引》(SCI);美国《工程索引》(EI);美国《生物学医学文摘》(MEDLINE);
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
  • 关键词

    sodium-cooled fast reactor; minor actinide-bearing fuel; core design;

    机译：钠冷快堆少量含act系元素的燃料;核心设计;

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