Comparison of steady and transient flow boiling critical heat flux for FeCrAl accident tolerant fuel cladding alloy, Zircaloy, and Inconel-Reference-Cited by-同舟云学术

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Comparison of steady and transient flow boiling critical heat flux for FeCrAl accident tolerant fuel cladding alloy, Zircaloy, and Inconel

Published:2019-04 Issue: Volume:132 Page:643-654
ISSN:0017-9310
Container-title:International Journal of Heat and Mass Transfer
language:en
Short-container-title:International Journal of Heat and Mass Transfer

Author:

Lee Soon K.,Liu Maolong,Brown Nicholas R.,Terrani Kurt A.,Blandford Edward D.,Ban Heng,Jensen Colby B.,Lee Youho

Funder

Nuclear Energy University Program

International Foundation for Research in Paraplegia

U.S. Department of Energy

Publisher

Elsevier BV

Subject

Fluid Flow and Transfer Processes,Mechanical Engineering,Condensed Matter Physics

Reference37 articles.

1. Accident tolerant fuels for LWRs: a perspective;Zinkle;J. Nucl. Mater.,2014

2. K.A. Terrani, T.M. Karlsen, Y. Yamamoto, Input correlations for irradiation creep of FeCrAl and SiC based on in-pile Halden test results, Technical Report ORNL/TM-2016/191, Oak Ridge National Laboratory, 2016.

3. An investigation of FeCrAl cladding behavior under normal operating and loss of coolant conditions;Gamble;J. Nucl. Mater.,2017

4. M.B. Cinbiz, N.R. Brown, R.R. Lowden, M.N. Gussev, K.D. Linton, K.A. Terrani, Report on Design and Failure Limits of SiC/SiC and FeCrAl ATF Cladding Concepts under RIA (No. ORNL/LTR-2018/521), Oak Ridge National Lab.(ORNL), Oak Ridge, TN, 2018.

5. Neutronic analysis of candidate accident-tolerant cladding concepts in pressurized water reactors;George;Ann. Nucl. Energy,2015

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