Sensitivity Analysis of Transient Critical Heat Flux by RIA Under High-Pressure Flow Boiling Conditions in TRTL-Reference-Cited by-同舟云学术

Sensitivity Analysis of Transient Critical Heat Flux by RIA Under High-Pressure Flow Boiling Conditions in TRTL

Published:2023-05-11 Issue:8 Volume:209 Page:1164-1188
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Meehan Nicholas A.¹^ORCID,Seo Seok Bin¹²,Howard Trevor K.³,Brown Nicholas R.¹^ORCID

Affiliation:

1. University of Tennessee Knoxville, Department of Nuclear Engineering, Knoxville, Tennessee

2. Idaho National Laboratory, Nuclear Science & Engineering, Idaho Falls, Idaho

3. Oregon State University, Nuclear Science and Engineering, Corvallis, Oregon

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/10.1080/00295450.2023.2195355

Reference70 articles.

1. Nuclear Fuel Behaviour Under Reactivity-Initiated Accident (RIA) Conditions, p. 13, Nuclear Energy Agency, Organisation for Economic Co-operation and Development (2010).

2. C. P. FOLSOM, “Fuel Performance Modeling of Reactivity-Initiated Accidents Using the BISON Code,” PhD Dissertation, Mechanical and Aerospace Engineering, Utah State University (Dec. 2017).

3. RIA Fuel Codes Benchmark, pp. 1 and 15, Nuclear Energy Agency, Organisation for Economic Co-operation and Development (2013).

4. Reactivity-Initiated Accident Fuel-Rod Code Benchmark Phase II: Uncertainty and Sensitivity Analyses, pp. 2 and 11, Nuclear Energy Agency, Organisation for Economic Co-operation and Development (2017).

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