Design of a prototypical natural circulation water-based reactor cavity cooling system (RCCS) for a pebble-bed generic FHR-Reference-Cited by-同舟云学术

Design of a prototypical natural circulation water-based reactor cavity cooling system (RCCS) for a pebble-bed generic FHR

Published:2023-06 Issue: Volume:407 Page:112303
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Talaat Khaled^ORCID,Chen Minghui

Funder

Office of Nuclear Energy

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

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3. Andreades, C., Cisneros, A.T., Choi, J.K., Chong, A.Y.K., Fratoni, M., Hong, S., Huddar, L.R., Huff, K.D., Krumwiede, D.L., Laufer, M.R., Munk, M., Scarlat, R.O., Zweibaum, N., Greenspan, E., Peterson, P., 2014. Technical Description of the “Mark 1” Pebble-Bed Fluoride-Salt-Cooled High-Temperature Reactor (PB-FHR) Power Plant.

4. Temperature-dependent properties of molten Li2BeF4 salt using Ab initio molecular dynamics;Baral;ACS Omega,2021

5. Reactor cavity cooling system (Rccs) experimental characterization;Capone;Nucl. Eng. Des.,2011

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