The AGR-like FHR reactor: Assessing the technical limits of the fuel-Reference-Cited by-同舟云学术

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The AGR-like FHR reactor: Assessing the technical limits of the fuel

Published:2024-07 Issue: Volume:423 Page:113180
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

de Lara A.^ORCID,Pizzocri D.,Van Uffelen P.,Shwageraus E.

Publisher

Elsevier BV

Reference31 articles.

1. Atkinson, K., 2021, Fuel performance engineer (EDF energy), Personal communication.

2. Gas-cooled nuclear reactor designs, operation and fuel cycle;Dawson,2002

3. Towards preliminary design calculations for application of Hastelloy cladding material;de Lara;Ann. Nucl. Energy,2023

4. AGR fuel design;Dickon,1988

5. Transuranus handbook;Dickon,2017

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. Consideration of Cr-doped UO2 fuel performance for a Fluoride-Cooled High Temperature Reactor concept;Annals of Nuclear Energy;2024-12

2. Preface for special issue “NFT-10: UK and ireland” − nuclear fission technology in UK and Ireland;Nuclear Engineering and Design;2024-11

3. Consideration of Cr-Doped Uo2 Fuel Performance for a Fluoride-Cooled High Temperature Reactor Concept;2024

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