Development of Conceptual Lead Cartridge Design to Perform Irradiation Experiments in VTR-Reference-Cited by-同舟云学术

Development of Conceptual Lead Cartridge Design to Perform Irradiation Experiments in VTR

Published:2022-01-10 Issue:sup1 Volume:196 Page:165-182
ISSN:0029-5639
Container-title:Nuclear Science and Engineering
language:en
Short-container-title:Nuclear Science and Engineering

Author:

Kim Seung Jun¹^ORCID,Woloshun Keith¹,Richard Joshua¹,Galloway Jack¹,Unal Cetin¹,Arndt Jeffrey²,Ickes Michael²,Ferroni Paolo²,Wright Richard²,Anderoglu Osman³,Cakez Cemal³,Talaat Khaled³,Ghosh Shuprio³,Bohannon Brandon³

Affiliation:

1. Los Alamos National Laboratory, P.O. Box 1663, Los Alamos, New Mexico, 87545

2. Westinghouse Electric Company, 1000 Westinghouse Drive, Cranberry Township, Philadelphia, 16066

3. University of New Mexico, 1 University of New Mexico, Albuquerque, New Mexico, 87131

Publisher

Informa UK Limited

Subject

Nuclear Energy and Engineering

Link

https://www.tandfonline.com/doi/pdf/10.1080/00295639.2021.2011572

Reference18 articles.

1. “Final Report on the Versatile Test Reactor Extended Length Test Assembly-Cartridge Lead (ELTA-CL) Pre-Conceptual Design,” LA-CP-20-20615, Los Alamos National Laboratory (Sep. 2020).

2. “Demonstration Lead-Cooled Fast Reactor Details: Westinghouse Lead-Cooled Fast Reactor,” Attachment 4, Westinghouse Electric Company; https://art.inl.gov/ART%20Document%20Library/Advanced%20Demonstration%20and%20Test%20Reactor%20Options%20Study/Attachment_4_Westinghouse_LFR_DR.pdf (current as of July 15, 2021).

3. M. S. EL-GENK et al. “Design Optimization and Performance of Miniature MHD and Gas-Lift Pumping Options for VTR Lead Extended Test Assembly (ELTA-CL),” Interim Progress Report, UNM-ISNPS-1-2020, University of New Mexico (June 2020).

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