DESIGN AND MANUFACTURE OF FUEL ASSEMBLIES FOR RUSSIAN RESEARCH REACTORS

机译：俄罗斯研究堆燃料组件的设计与制造

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

The most widely distributed fuel assembly designs with tubular fuel elements (WWR-M2, WWR-M5, IRT-2M, IRT-3M, MR, MIR, WWR-TS, IVV-2M) with more than 20% U-235 enrichment nuclear fuel used in research reactors of Russian design are described. rnThe results of activities to convert foreign research reactors of Russian design to low-enrichment (less than 20% U-235) fuel that are performed in accordance with the Russian Program on Reduced Enrichment of Research Reactors are presented. rnFinally, recent accreditation of quality assurance (QA) and safety practices at the Novosibirsk Chemical Concentrate Plant (NCCP) to international standards is described.

机译：分布最广泛的燃料组件设计，其管状燃料元件（WWR-M2，WWR-M5，IRT-2M，IRT-3M，MR，MIR，WWR-TS，IVV-2M）具有20％以上的U-235浓缩核描述了俄罗斯设计的研究堆中使用的燃料。 rn介绍了根据俄罗斯减少研究堆浓缩计划执行的将俄罗斯设计的国外研究堆转化为低浓度（U-235含量低于20％）燃料的活动结果。最后，描述了新西伯利亚化学浓缩工厂（NCCP）最近的质量保证（QA）和安全实践认证达到国际标准。

著录项

来源
《Safety Related Issues of Spent Nuclear Fuel Storage; NATO Security Through Science Series C: Environmental Security》|2005年|95-105|共11页
会议地点 Almaty(KZ)
作者
V. V. ROZHIKOV; A. A. ENIN; A. B. ALEXANDROV; A. A. TKACHEV;
展开▼
作者单位

OAO Novosibirsk Chemical Concentrate Plant, 94, Khmelnizkiy St., Novosibirsk 30110, Russia;

展开▼
会议组织
原文格式 PDF
正文语种 eng
中图分类 TL388;
关键词
research reactors, tubular fuel pins, U-Al alloy, UO_2-Al, U-9 Mo, low-enrichment uranium (LEU) fuels, ISO-9001-2000 and ISO-14001-98 standards;

机译：研究堆，管状燃料棒，U-铝合金，UO_2-Al，U-9％Mo，低浓铀（LEU）燃料，ISO-9001-2000和ISO-14001-98标准;

相似文献

外文文献
中文文献
专利

1. Reactor physics and safety aspects of various design options of a Russian light water reactor with rock-like fuels [J] . Bondarenko A., Komissarov O., Komenkov YK., Journal of Nuclear Materials: Materials Aspects of Fission and Fusion . 2003,第0期

机译：带有岩石状燃料的俄罗斯轻水反应堆各种设计方案的反应堆物理和安全方面
2. Test assemblies of accident tolerant fuel set for Russian reactor use [J] . Vladislav Vorotnikov Platts Nuclear Fuel . 2019,第26期

机译：俄罗斯反应堆使用的容错燃料的测试组件
3. Fuel Cycle Analysis of Novel Assembly Design for Thorium- Uranium-Ceramic-Fueled Thermal, High-Conversion Reactor [J] . N. Kaffezakis, D. Kotlyar Nuclear Technology . 2020,第1期

机译：Thor-铀-陶瓷燃料热高转化反应堆新型装配设计的燃料循环分析
4. DESIGN AND MANUFACTURE OF FUEL ASSEMBLIES FOR RUSSIAN RESEARCH REACTORS [C] . V. V. ROZHIKOV, A. A. ENIN, A. B. ALEXANDROV, NATO Advanced Research Workshop on Safety Related Issues of Spent Nuclear Fuel Storage . 2007

机译：俄罗斯研究反应堆燃料组件的设计与制造
5. The design, assembly and performance testing of a 1 kW steam reforming reactor for processing diesel fuel [D] . Harasti, Peter T. 2004

机译：用于处理柴油的1 kW蒸汽重整反应器的设计，组装和性能测试
6. Design and Evaluation of a Co–Mo-SupportedNano Alumina Ultradeep Hydrodesulfurization Catalyst for Productionof Environmentally Friendly Diesel Fuel in a Trickle Bed Reactor [O] . Saad A. Awad, Saba A. Gheni, Ghassan H. Abdullah, 2020

机译：Co-Mo支持的设计和评估纳米氧化铝超深度加氢脱硫催化剂的生产Bed流床反应器中的环保柴油燃料
7. Morning light cleanup and recovery operation: simulation studies of possible reactor fuels. Cosmos 954 orbiting Russian reactor with U-10 wt Mo fuel [O] . R.L. Landingham, A.W. Casey 1978

机译：晨光清理和恢复操作：可能的反应堆燃料的仿真研究。 Cosmos 954轨道俄罗斯反应堆与U-10 wt％Mo燃料

DESIGN AND MANUFACTURE OF FUEL ASSEMBLIES FOR RUSSIAN RESEARCH REACTORS

摘要

著录项

相似文献

相关主题

期刊订阅