Structural Integrity Assessment of a Nuclear Vessel through ASME and Master Curve Approaches Using Irradiation Embrittlement Predictions-Reference-Cited by-同舟云学术

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Structural Integrity Assessment of a Nuclear Vessel through ASME and Master Curve Approaches Using Irradiation Embrittlement Predictions

Published:2019-01-08 Issue:6 Volume:48 Page:20180569
ISSN:0090-3973
Container-title:Journal of Testing and Evaluation
language:en
Short-container-title:J. Test. Eval.

Author:

Ferreño Diego¹,Fernández-Rucoba David²,Casado José A.³,Bascones Roberto²,Ruiz Estela³,Rodríguez Álvaro²,Miguel Roberto⁴,Poncela Enrique G.⁴

Affiliation:

1. Laboratory of Science and Engineering of Materials, University of Cantabria, E.T.S. de Ingenieros de Caminos, Canales y Puertos, Av. Los Castros 44, Santander 39005, Spain (Corresponding author), e-mail: ferrenod@unican.es

2. Technological Centre for Components, Parque Científico y Tecnológico de Cantabria C/ Isabel Torres n° 1, Santander 39011, Spain

3. Laboratory of Science and Engineering of Materials, University of Cantabria, E.T.S. de Ingenieros de Caminos, Canales y Puertos, Av. Los Castros 44, Santander 39005, Spain

4. Equipos Nucleares, S.A., S.M.E. Av. Juan Carlos I, 8, Maliaño 39600, Spain

Publisher

ASTM International

Subject

Mechanical Engineering,Mechanics of Materials,General Materials Science

Cited by 1 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Development of pressure-temperature limit curves considering unified constraint for reactor pressure vessel;International Journal of Pressure Vessels and Piping;2024-02

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