Feasibility study of a prestressed-concrete containment vessel for a novel GFR nuclear reactor-Reference-Cited by-同舟云学术

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Feasibility study of a prestressed-concrete containment vessel for a novel GFR nuclear reactor

Published:2023-07 Issue: Volume:286 Page:116119
ISSN:0141-0296
Container-title:Engineering Structures
language:en
Short-container-title:Engineering Structures

Author:

Holan Jakub^ORCID,Bílý Petr,Štefan Radek^ORCID,Vácha Petr

Funder

České Vysoké Učení Technické v Praze

Technology Agency of the Czech Republic

Publisher

Elsevier BV

Subject

Civil and Structural Engineering

Reference45 articles.

1. Generation IV Systems;The Generation IV International Forum,2022

2. Generation IV nuclear reactors: Current status and future prospects;Locatelli;Energy Policy,2013

3. Handbook of generation IV nuclear reactors;Pioro,2016

4. 4 - Current and future nuclear power reactors and plants;Pioro,2019

5. Chapter 9 - Nuclear fission;Gill,2014

Cited by 3 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. Review of the transmittance effects and long-term radiation mechanisms of γ on heavy concrete;Progress in Nuclear Energy;2024-10

2. Effects of Prestressing Magnitude and Position on Seismic Performance of Unbonded Prestressed Concrete Beams;Buildings;2024-02-04

3. Modelling of Steel-Concrete-Steel Structure Using FEM Plane Elements;Lecture Notes in Civil Engineering;2023-10-25

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