首页> 美国政府科技报告 >Tests of Types 51A and 51M Steam Generators at Bugey 4 and Tricastin 1 Nuclear Power Plants. Final Report

【24h】

Tests of Types 51A and 51M Steam Generators at Bugey 4 and Tricastin 1 Nuclear Power Plants. Final Report

机译：Bugey 4和Tricastin 1核电站的51a和51m型蒸汽发生器的试验。总结报告

获取原文

页面导航

摘要
著录项
相似文献
相关主题

摘要

Following some incidents on a number of US steam generators (SGs), alterations were made to the Westinghouse SGs of series 51 installed on the EDF 900 MW units. To check the merits of these alterations and to better understand the operation of this equipment, a series of tests were run on SG No. 14 of Bugey 4 and No. 20 of Tricastin 1 nuclear units. The tests results are described. (ERA citation 08:005062)

著录项

作者
Procaccia, H.; David, J.; de Penguern, L.; Hamon, P.; Wazzan, A. R.;
展开▼
作者单位

展开▼
年度 1982
页码 1-180
总页数 180
原文格式 PDF
正文语种 eng
中图分类工业技术;
关键词
Pwr type reactors; Steam generators; Hydraulics; Heat transfer; Temperature distribution;

机译：pwr型反应器;蒸汽发生器;液压;传热;温度分布;

相似文献

外文文献
中文文献
专利

1. Influence of molybdenum disulfide on the cracking of corrosion-resistant materials of steam generators of nuclear power plants. [J] . R.K.Melekov Materials Science . 1998,第6期

机译：二硫化钼对核电站蒸汽发生器耐腐蚀材料开裂的影响。
2. Preoperational Tests of the PIRATE Program for Identifying and Assessing the Depth of Defects in Heat Exchangers of Nuclear Power Plants' Steam Generators [J] . A. G. Zhdanov, V. P. Lunin, A. A. Stolyarov, Thermal engineering . 2020,第8期

机译：用于识别和评估核电站蒸汽发生器热交换器中缺陷深度的海盗计划的术前试验
3. Stochastic Nondestructive Testing Simulation: Sensitivity Analysis Applied to Material Properties in Clogging of Nuclear Powerplant Steam Generators [J] . Moreau O., Beddek K., Clenet S., Magnetics, IEEE Transactions on . 2013,第5期

机译：随机无损测试模拟：灵敏度分析应用于核电厂蒸汽发生器堵塞的材料特性
4. Fouling Of Steam Generator Tubes In Nuclear Power Plants: Laboratory Tests To Reproduce Oxides Deposition And Chemical Cleanings [C] . C. Goujon, A. Bescond, C. Mansour, Nuclear Plant Chemistry Conference . 2015

机译：核电厂蒸汽发生器管的污染：重现氧化物沉积和化学清洁的实验室测试
5. LUMPED PARAMETER, STATE VARIABLE DYNAMIC MODELS FOR U-TUBE RECIRCULATION TYPE NUCLEAR STEAM GENERATORS. [D] . ALI, MOHAMED RABIE AHMED -1

机译：U型管循环型核蒸汽发生器的集总参数，状态变量动态模型。
6. A novel inspection robot for nuclear station steam generator secondary side with self-localization [O] . Jinke Li, Xinyu Wu, Tiantian Xu, -1

机译：具有自定位功能的新型核电站蒸汽发生器二次侧检查机器人
7. On-line testing of calibration of process instrumentation channels in nuclear power plants. Phase 2, Final report [O] . Hashemian, H.M. 1995

机译：核电厂过程仪表通道校准的在线测试。第2阶段，最终报告
8. Tests of Types 51A and 51M Steam Generators at Bugey 4 and Tricastin 1 Nuclear Power Plants [R] . 1982

机译：Bugey 4和Tricastin 1核电站的51a和51m型蒸汽发生器的试验

Tests of Types 51A and 51M Steam Generators at Bugey 4 and Tricastin 1 Nuclear Power Plants. Final Report

摘要

著录项

相似文献

相关主题

期刊订阅