首页> 外文OA文献 >Feasibility Study for Evaluation of Control Rod Worth in Pressurized Water Reactors using Neutron Count Rate during a Control Rod Drop Testing

【2h】

Feasibility Study for Evaluation of Control Rod Worth in Pressurized Water Reactors using Neutron Count Rate during a Control Rod Drop Testing

机译：在控制棒跌落测试中使用中子计数率评估压水堆中控制棒价值的可行性研究

页面导航

著录项
相似文献
相关主题

著录项

作者
Yoichiro Shimazu; Kennichiro Okazaki; Masashi Tsuji;
展开▼
作者单位

展开▼
年度 2006
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. Feasibility Study for Evaluation of Control Rod Worth in Pressurized Water Reactors using Neutron Count Rate during a Control Rod Drop Testing [J] . Yoichiro SHIMAZU, Kennichiro OKAZAKI, Masashi TSUJI Journal of nuclear science and technology . 2006,第8期

机译：在控制棒下落试验中使用中子计数率评估压水堆控制棒价值的可行性研究
2. Examination of Actual Neutron Count Rate Data during a Control Rod Drop Testing for Estimation of Control Rod Worth in PWRs [J] . Yoichiro SHIMAZU, Masashi TSUJI, Tadashi NARABAYASHI Journal of nuclear science and technology . 2011,第3期

机译：在控制棒跌落测试期间检查实际中子计数率数据以估算压水堆中的控制棒价值
3. Optimization of the worth shape of axially variable strength control rods with simulation optimization methodology for the power maneuvering of pressurized water reactors [J] . Ung-Soo Kim, Poong-Hyun Seong Nuclear Engineering and Design . 2003,第1期

机译：利用压水堆动力操纵的仿真优化方法优化轴向可变强度控制棒的形状
4. Evaluation of Control Rod Worth in Pressurized Water Reactors Using Neutron Count Rate during a Control Rod Drop Testing [C] . Kenichiro OKAZAKI, Yoichiro SHIMAZU, Masashi TUJI International Congress on Advances in Nuclear Power Plants . 2007

机译：控制杆下降试验期间使用中子计数率在加压水反应器中的控制棒评估
5. Experimental and Numerical Investigation of Pressure Drop in Silicon Carbide Fuel Rod for Application in Pressurized Water Reactors. [D] . Abir, Ahmed Musafi. 2017

机译：用于压水堆的碳化硅燃料棒压降的实验和数值研究。
6. Pb(Mg1/3Nb2/3)-PbTiO3-Based Ultrasonic Transducer for Detecting Infiltrated Water in Pressurized Water Reactor Fuel Rods [O] . Geonwoo Kim, Namkyoung Choi, Yong-Il Kim, 2019

机译：基于Pb（Mg1 / 3Nb2 / 3）-PbTiO3的超声波换能器用于检测压水堆燃料棒中的渗透水
7. Examination of Actual Neutron Count Rate Data during a Control Rod Drop Testing for Estimation of Control Rod Worth in PWRs [O] . Yoichiro SHIMAZU, Masashi TSUJI, Tadashi NARABAYASHI 2011

机译：检查控制杆下降试验期间的实际中子计数数据，以估算PWR的控制杆价值
8. CONTROL ROD THEORIES EVALUATION BASED UPON MEASUREMENTS OF CONTROL ROD WORTHS IN SM-I-2 REACTOR ASSEMBLIES [R] . J.W.Zwick 1959

机译：基于sm-I-2反应堆组件控制杆测量的控制杆理论评估

Feasibility Study for Evaluation of Control Rod Worth in Pressurized Water Reactors using Neutron Count Rate during a Control Rod Drop Testing

著录项

相似文献

相关主题

期刊订阅