Eine Plattform für die Wissenschaft: Bauingenieurwesen, Architektur und Urbanistik
Effects of Prior Deformation and Prior Immersion in Simulated Pressurized Water Reactor Primary Water on Tensile Properties of Alloy 690
Effects of Prior Deformation and Prior Immersion in Simulated Pressurized Water Reactor Primary Water on Tensile Properties of Alloy 690
Effects of Prior Deformation and Prior Immersion in Simulated Pressurized Water Reactor Primary Water on Tensile Properties of Alloy 690
Xia, Xiao-feng (Autor:in) / Lü, Zhan-peng (Autor:in) / Chen, Jun-jie (Autor:in)
Fu shi yu fang hu ; 36 ; 170-176
01.01.2015
7 pages
Aufsatz (Zeitschrift)
Unbekannt
DDC:
620.11223
© Metadata Copyright the British Library Board and other contributors. All rights reserved.
British Library Online Contents | 2008
|The oxidation of alloy 690 in simulated pressurized water reactor primary water
British Library Online Contents | 2017
|The oxidation of alloy 690 in simulated pressurized water reactor primary water
British Library Online Contents | 2017
|Stress Corrosion Cracking Growth of Alloy 800NG in Pressurized Water Reactor Primary Water
British Library Online Contents | 2018
|British Library Online Contents | 2006
|