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Volume 207

Number 10

Table of Contents

Integrating Advanced Modeling and Accelerated Testing for a Modernized Fuel Qualification Paradigm

G. L. Beausoleil, C. Petrie, W. Williams, A. Jokisaari, L. Capriotti, S. Novascone, C. Adkins, M. Kerr

Nuclear Technology / Volume 207 / Number 10 / October 2021 / Pages 1491-1510

Critical Review / dx.doi.org/10.1080/00295450.2020.1826272

Sensitivity Studies to Assess the Impact of Geometry and Operating/Boundary Condition Perturbations on Thermal-Hydraulic Behavior of Advanced Fuel Channels in Pressure Tube Heavy Water Reactors with Uranium and Thorium-Based Fuels

B. P. Bromley, Z. Cheng, A. Nava Dominguez, A. V. Colton

Nuclear Technology / Volume 207 / Number 10 / October 2021 / Pages 1511-1537

Technical Paper / dx.doi.org/10.1080/00295450.2020.1827658

Startup Test Plan and Predictions for Highly Enriched Uranium to Low-Enriched Uranium Fuel Conversion at the University of Missouri Research Reactor

Wilson Cowherd, John Stillman, Leslie Foyto, Erik Wilson, Kiratadas Kutikkad, Nickie Peters, John Gahl

Nuclear Technology / Volume 207 / Number 10 / October 2021 / Pages 1538-1563

Technical Paper / dx.doi.org/10.1080/00295450.2020.1829427

Multi-Index Measurement of Fatigue Degree Under the Simulated Monitoring Task of a Nuclear Power Plant

Gang Zhang, Shibo Mei, Kaijie Xie, Zhen Yang

Nuclear Technology / Volume 207 / Number 10 / October 2021 / Pages 1564-1577

Technical Paper / dx.doi.org/10.1080/00295450.2020.1824965

Modeling Tritium Retention in Graphite for Fluoride-Salt-Cooled High-Temperature Reactors

Kieran Dolan, Steven Huang, Micah Hackett, Lin-Wen Hu

Nuclear Technology / Volume 207 / Number 10 / October 2021 / Pages 1578-1598

Technical Paper / dx.doi.org/10.1080/00295450.2020.1829428

Coupled Computational Fluid Dynamics–Discrete Element Method Study of Bypass Flows in a Pebble Bed Reactor

Mauricio E. Tano, Jean C. Ragusa

Nuclear Technology / Volume 207 / Number 10 / October 2021 / Pages 1599-1614

Technical Paper / dx.doi.org/10.1080/00295450.2020.1820830

Comparison of Triggered Steam Explosion Behavior According to Corium Injection Mode in TROI Facility from TEXAS-V Code Simulations

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

Nuclear Technology / Volume 207 / Number 10 / October 2021 / Pages 1615-1632

Technical Paper / dx.doi.org/10.1080/00295450.2020.1820827

On the Amount of Moderation in the CANDU Lattice

Benjamin Rouben, Eleodor Nichita

Nuclear Technology / Volume 207 / Number 10 / October 2021 / Pages 1633-1638

Technical Note / dx.doi.org/10.1080/00295450.2020.1827884

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