Two-Step Procedure for Liquid-Salt-Cooled-Reactor Analysis-Reference-Cited by-同舟云学术

Two-Step Procedure for Liquid-Salt-Cooled-Reactor Analysis

Published:2018-07-17 Issue:3 Volume:204 Page:299-317
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Gentry Cole¹^ORCID,Kim Kang Seog¹,Maldonado G. Ivan²

Affiliation:

1. Oak Ridge National Laboratory, Reactor and Nuclear Systems Division, Oak Ridge, Tennessee

2. University of Tennessee, Knoxville, Department of Nuclear Engineering, Knoxville, Tennessee 37996-2300

Funder

U.S. Department of Energy

Publisher

Informa UK Limited

Subject

Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Link

https://www.tandfonline.com/doi/pdf/10.1080/00295450.2018.1486158

Reference23 articles.

1. D. E. HOLCOMB et al. “Core and Refueling Design Studies for the Advanced High Temperature Reactor,” ORNL/TM-2011/365, Oak Ridge National Laboratory (2011).

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

3. K. S. SMITH, “Spatial Homogenization Methods For Light Water Reactor Analysis,” Doctoral Dissertation, Massachusetts Institute of Technology (1980).

4. D. F. WILLIAMS, L. M. TOTH, and K. T. CLARNO, “Assessment of Candidate Molten Salt Coolants for the Advanced High-Temperature Reactor (AHTR),” ORNL/TM-2006/12, Oak Ridge National Laboratory (2006).

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