首页> 外文OA文献 >Overall System Description and Safety Characteristics of Prototype Gen IV Sodium Cooled Fast Reactor in Korea

【2h】

Overall System Description and Safety Characteristics of Prototype Gen IV Sodium Cooled Fast Reactor in Korea

机译：韩国原型第四代钠冷却快堆的整体系统描述和安全特性

代理获取

本网站仅为用户提供外文OA文献查询和代理获取服务，本网站没有原文。下单后我们将采用程序或人工为您竭诚获取高质量的原文，但由于OA文献来源多样且变更频繁，仍可能出现获取不到、文献不完整或与标题不符等情况，如果获取不到我们将提供退款服务。请知悉。

页面导航

著录项
引文网络
相似文献
相关主题

著录项

作者
Jaewoon Yoo; Jinwook Chang; Jae-Yong Lim; Jin-Sik Cheon; Tae-Ho Lee; Sung Kyun Kim; Kwi Lim Lee; Hyung-Kook Joo;
展开▼
作者单位

展开▼
年度 2016
总页数
原文格式 PDF
正文语种
中图分类

相似文献

外文文献
中文文献
专利

1. Overall System Description and Safety Characteristics of Prototype Gen IV Sodium Cooled Fast Reactor in Korea [J] . Yoo Jaewoon, Chang Jinwook, Lim Jae-Yong, Nuclear engineering and technology . 2016,第5期

机译：韩国第四代钠冷快堆的总体系统描述和安全特性
2. Overall System Description and Safety Characteristics of Prototype Gen IV Sodium Cooled Fast Reactor in Korea [J] . Jaewoon Yoo, Jinwook Chang, Jae-Yong Lim, Nuclear engineering and technology . 2016,第5期

机译：韩国第四代钠冷快堆的总体系统描述和安全特性
3. Overall Reactor System Description of Prototype Gen-Ⅳ Sodium Cooled Fast Reactor [J] . Jaewoon Yoo, Jinwook Chang, Hyung-Kook Joo Transactions of the American nuclear society . 2016,第juna期

机译：第四代原型钠冷快堆的总体反应器系统描述
4. Multi-discipline Considered Design of Reactor Shutdown System for Prototype GEN-IV Sodium-cooled Fast Reactor [C] . Kyungho Yoon, Hyun-Seung Lee International congress on advances in nuclear power plants . 2018

机译：GEN-IV型钠冷快堆的反应堆关闭系统的多学科考虑设计
5. Effects of fuel type on the safety characteristics of a sodium cooled fast reactor. [D] . Sumner, Tyler. 2010

机译：燃料类型对钠冷快堆安全特性的影响。
6. Effects of Bi2O3 Doping on the Mechanical Properties of PbO Ceramic Pellets Used in Lead-Cooled Fast Reactors [O] . Yan Ma, Anxia Yang, Huiping Zhu, 2019

机译：Bi2O3掺杂对铅冷快堆中PbO陶瓷颗粒力学性能的影响
7. Overall System Description and Safety Characteristics of Prototype Gen IV Sodium Cooled Fast Reactor in Korea [O] . Yoo Jaewoon, Chang Jinwook, Lim Jae-Yong, 2016

机译：韩国第四代钠冷快堆的总体系统描述和安全特性
8. Liquid salt - very high temperature reactor : survey of sodium-cooled fast reactor fuel handling systems for relevant design and operating characteristics. [R] . 2006

机译：液体盐 - 极高温反应堆：调查钠冷却快堆燃料处理系统的相关设计和操作特性。

Overall System Description and Safety Characteristics of Prototype Gen IV Sodium Cooled Fast Reactor in Korea

著录项

引文网络

相似文献

相关主题

期刊订阅