Natural Circulation and Linear Stability Analysis for Liquid-Metal Reactors with the Effect of Fluid Axial Conduction-Reference-Cited by-同舟云学术

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Natural Circulation and Linear Stability Analysis for Liquid-Metal Reactors with the Effect of Fluid Axial Conduction

Published:2012-06 Issue:3 Volume:178 Page:298-317
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Sabharwall Piyush¹,Yoo Yeon Jong²,Wu Qiao³,Sienicki James J.⁴

Affiliation:

1. Idaho National Laboratory, P.O. Box 1625, Idaho Falls, Idaho 83415-3730

2. NuScale Power, 1100 NE Circle Boulevard, Suite 350, Corvallis, Oregon 97330

3. Oregon State University, Nuclear Engineering Department, Corvallis, Oregon 97330

4. Argonne National Laboratory, 9700 South Cass Avenue, Argonne, Illinois 60439

Publisher

Informa UK Limited

Subject

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

Link

https://www.tandfonline.com/doi/pdf/10.13182/NT12-A13595

Reference11 articles.

1. Status of Research and Development of the Lead-Alloy-Cooled Fast Reactor

2. Periodic oscillations in a model of thermal convection

3. On the oscillatory instability of a differentially heated fluid loop

4. Stability characteristics of a single-phase free convection loop

5. Simulation of the unstable oscillatory behavior of single-phase natural circulation with repetitive flow reversals in a rectangular loop using the computer code athlet

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2. Numerical analysis of dynamic load following response in a natural circulation molten salt power reactor system;Nuclear Engineering and Design;2022-08

3. Reliability analysis of passive systems: An overview, status and research expectations;Progress in Nuclear Energy;2022-01

4. Prediction of PbLi fluid flow and temperature field in a thermal convection loop for qualification of fusion materials;International Journal of Heat and Mass Transfer;2021-06

5. Natural circulation experiments in a non-uniform diameter lead bismuth loop and validation of LeBENC code;Progress in Nuclear Energy;2016-08

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