Analysis of KROTOS Steam Explosion Experiments Using the Improved Fuel-Coolant–Interaction Code TEXAS-VI-Reference-Cited by-同舟云学术

Analysis of KROTOS Steam Explosion Experiments Using the Improved Fuel-Coolant–Interaction Code TEXAS-VI

Published:2013-05 Issue:1 Volume:174 Page:46-59
ISSN:0029-5639
Container-title:Nuclear Science and Engineering
language:en
Short-container-title:Nuclear Science and Engineering

Author:

Chen R. H.¹²,Corradini M. L.¹,Su G. H.²,Qiu S. Z.²

Affiliation:

1. Xi’an Jiaotong University, Department of Nuclear Science and Technology, Xi’an, 710049, China

2. University of Wisconsin-Madison, College of Engineering, Nuclear Engineering and Engineering Physics, Madison, Wisconsin 53706

Publisher

Informa UK Limited

Subject

Nuclear Energy and Engineering

Link

https://www.tandfonline.com/doi/pdf/10.13182/NSE12-22

Reference25 articles.

1. “Reactor Safety Study: An Assessment of Accident Risks in U.S. Commercial Nuclear Power Plants,” WASH-1400, NUREG-7500114, U.S. Nuclear Regulatory Commission (Oct. 1975).

2. High pressure corium melt quenching tests in FARO

3. Fuel coolant interaction experiments in TROI using a UO2/ZrO2 mixture

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