Lead Fast Reactor Thermal-Hydraulic Testing Facilities in Support of the UK Advanced Modular Reactor Program-Reference-Cited by-同舟云学术

Lead Fast Reactor Thermal-Hydraulic Testing Facilities in Support of the UK Advanced Modular Reactor Program

Published:2024-07-02 Issue: Volume: Page:1-11
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Liao J.¹^ORCID,Stansbury C. A.¹,Durse M. E.¹,Wise D. L.¹,Tatli E.¹,Loebig T. G.¹,Wright R. F.¹,Ferroni P.¹,Lee S. J.²,Epstein M.²,Caramello M.³,Frignani M.³,Tarantino M.⁴,Grasso G.⁴,Di Piazza I.⁴,Bassini S.⁴,Lorusso P.⁴,Antonelli A.⁴,Martelli D.⁴,Wimshurst A.⁵,Watkins R.⁵,Macpherson G.⁵,Wilson D.⁶,Iacovides H.⁶,Cioncolini A.⁶,Francis J.⁶,Buckley J.⁶

Affiliation:

1. Westinghouse Electric Company, Safety Analysis, Cranberry Township, Pennsylvania

2. Fauske & Associates, LLC, Burr Ridge, Illinois

3. Ansaldo Nuclear Ltd, Wolverhampton, United Kingdom

4. Italian National Agency for New Technologies, Energy and Sustainable Economic Development (ENEA), Bologna, Italy

5. Frazer-Nash Consulting, Bristol, United Kingdom

6. The University of Manchester, Manchester, United Kingdom

Funder

Department of BEIS

Publisher

Informa UK Limited

Link

https://www.tandfonline.com/doi/pdf/10.1080/00295450.2024.2361187

Reference21 articles.

1. “Advances in Small Modular Reactor Technology Developments ” IAEA Advanced Reactors Information System (ARIS) 2022 Edition; International Atomic Energy Agency; https://aris.iaea.org/Publications/SMR_booklet_2022.pdf.

2. P. FERRONI et al., “The Westinghouse Lead Fast Reactor: Overview and Update on Development Program,” Proc. Int. Congress on Advances in Nuclear Power Plants (ICAPP), Gyeongju, Korea (2023).

3. Development of phenomena identification and ranking table for Westinghouse lead fast reactor's safety

4. J. LIAO et al., “Progress of Lead Fast Reactor Testing Facilities in the UK Advanced Modular Reactor Program,” Proc. Int. Congress on Advances in Nuclear Power Plants (ICAPP), Gyeongju, Korea (2023).

5. M. CARAMELLO et al., “Testing Innovative Decay Heat Removal System through the Passive Heat Removal Facility (PHRF): Facility Description and Early Testing in Support to Lead Fast Reactor Development,” Proc. 20th Int. Topl. Mtg. on Nuclear Reactor Thermal Hydraulics, Washington, DC, August 20–25, 2023.