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Volume 206

Number 3

Liquid Film Thickness in Vertical Circular Pipes Under Flooding Conditions at the Top End

Toshiya Takaki, Michio Murase, Koji Nishida, Raito Goda, Takeyuki Shimamura, Akio Tomiyama

Nuclear Technology / Volume 206 / Number 3 / March 2020 / Pages 389-400

Technical Paper / dx.doi.org/10.1080/00295450.2019.1656521

Comparison of Triggered Explosion Behavior by Corium Injection Modes in TROI Facility

Seong-Wan Hong, Sang Ho Kim, Rae-Joon Park

Nuclear Technology / Volume 206 / Number 3 / March 2020 / Pages 401-413

Technical Paper / dx.doi.org/10.1080/00295450.2019.1654816

Uncertainty Quantification Using the MAAP5 Code of In-Vessel Hydrogen Generation in a Severe Accident at an Advanced Boiling Water Reactor

Te-Chuan Wang, Min Lee

Nuclear Technology / Volume 206 / Number 3 / March 2020 / Pages 414-427

Technical Paper / dx.doi.org/10.1080/00295450.2019.1653152

The CRANK System—A Simple, Robust Apparatus for Measurement of Cherenkov Light at Open-Pool Reactor

Thomas V. Holschuh, Wade R. Marcum

Nuclear Technology / Volume 206 / Number 3 / March 2020 / Pages 428-434

Technical Paper / dx.doi.org/10.1080/00295450.2019.1640515

Development of an In-Vessel CEDM for Small Modular Reactors

Jinseok Park, Wonho Lee, Myounggoo Lee, Yeonho Cho, Hyunmin Kim, Chulsoo Maeng

Nuclear Technology / Volume 206 / Number 3 / March 2020 / Pages 435-443

Technical Paper / dx.doi.org/10.1080/00295450.2019.1635363

A Revised Capsule Design for the Accelerated Testing of Advanced Reactor Fuels

G. L. Beausoleil, II, G. L. Povirk, B. J. Curnutt

Nuclear Technology / Volume 206 / Number 3 / March 2020 / Pages 444-457

Technical Paper / dx.doi.org/10.1080/00295450.2019.1631052

Experimental and Simulation Analysis of Hydrogen Permeation Performance of Pd/Ag Permeator Used for Tritium Processing

Yu Huang, Gaofeng Lu, Youshi Zeng, Nan Qian, Xinxin Chu, Guanghua Wang, Shengwei Wu, Wei Liu

Nuclear Technology / Volume 206 / Number 3 / March 2020 / Pages 458-466

Technical Paper / dx.doi.org/10.1080/00295450.2019.1633156

Effectiveness of Cr-Coated Zr-Alloy Clad in Delaying Fuel Degradation for a PWR During a Station Blackout Event

J. Wang, H. Yeom, P. Humrickhouse, K. Sridharan, M. Corradini

Nuclear Technology / Volume 206 / Number 3 / March 2020 / Pages 467-477

Technical Paper / dx.doi.org/10.1080/00295450.2019.1649566

Demonstration of the Advanced Dynamic System Modeling Tool TRANSFORM in a Molten Salt Reactor Application via a Model of the Molten Salt Demonstration Reactor

M. Scott Greenwood, Benjamin R. Betzler, A. Lou Qualls, Junsoo Yoo, Cristian Rabiti

Nuclear Technology / Volume 206 / Number 3 / March 2020 / Pages 478-504

Technical Paper / dx.doi.org/10.1080/00295450.2019.1627124

Conceptual Design of an Accident Prevention System for Light Water Reactors Using Artificial Neural Network and High-Speed Simulator

Li-Chi Cliff Po

Nuclear Technology / Volume 206 / Number 3 / March 2020 / Pages 505-513

Technical Note / dx.doi.org/10.1080/00295450.2019.1641877

Characteristics of Water Suction for a Korean Compacted Bentonite

Seok Yoon, Jun-Seo Jeon, Seeun Chang, Deuk-Hwan Lee, Seung-Rae Lee, Geon-Young Kim

Nuclear Technology / Volume 206 / Number 3 / March 2020 / Pages 514-525

Technical Note / dx.doi.org/10.1080/00295450.2019.1632093

 

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