Thermal-Hydraulic System-Level Analysis of a Molten Salt Natural Circulation Loop-Reference-Cited by-同舟云学术

Thermal-Hydraulic System-Level Analysis of a Molten Salt Natural Circulation Loop

Published:2022-08-25 Issue:5 Volume:197 Page:920-946
ISSN:0029-5639
Container-title:Nuclear Science and Engineering
language:en
Short-container-title:Nuclear Science and Engineering

Author:

Zhang Sheng¹^ORCID,Lin Hsun-Chia¹²,Sun Xiaodong¹

Affiliation:

1. University of Michigan, Department of Nuclear Engineering and Radiological Sciences, Ann Arbor, Michigan 48109

2. Argonne National Laboratory, Nuclear Science and Engineering Division, Lemont, Illinois 60439

Funder

Department of Energy Office of Nuclear Energy’s Nuclear Energy University Program

Publisher

Informa UK Limited

Subject

Nuclear Energy and Engineering

Link

https://www.tandfonline.com/doi/pdf/10.1080/00295639.2022.2102389

Reference42 articles.

1. W. VARMA et al. “AHTR Mechanical, Structural, and Neutronic Preconceptual Design,” ORNL/TM-2012/320, Oak Ridge National Laboratory (2012).

2. S. R. GREENE et al. “Pre-Conceptual Design of a Fluoride-Salt-Cooled Small Modular Advanced High-Temperature Reactor (SmAHTR),” ORNL/TM-2010/199, Oak Ridge National Laboratory (2010).

3. C. H. ANDREADES, A. T. CISNEROS, and J. K. CHOI, “Technical Description of the ‘Mark 1’ Pebble-Bed Fluoride-Salt-Cooled High-Temperature Reactor (PB-FHR) Power Plant,” UCBTH-14-002, University of California, Berkeley, California (2014).

4. “Design Overview for the Kairos Power Fluoride Salt-Cooled High-Temperature Reactor,” KP-NRC-1811-002, Kairos Power, LLC (2018).

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