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Volume 207

Number 5

Thermal-Hydraulic and Engineering Evaluations of New LOCA Testing Methods in TREAT

Nicolas Woolstenhulme, Colby Jensen, Charles Folsom, Robert Armstrong, Junsoo Yoo, Daniel Wachs

Nuclear Technology / Volume 207 / Number 5 / May 2021 / Pages 637-652

Technical Paper / dx.doi.org/10.1080/00295450.2020.1807280

TRACE Analysis of a Loss of Alternating-Current Power Without Rod Insertion for the NuScale Power Module—I: Basic Event Progression and Long-Term Behavior

Peter Yarsky

Nuclear Technology / Volume 207 / Number 5 / May 2021 / Pages 653-664

Technical Paper / dx.doi.org/10.1080/00295450.2020.1800308

TRACE Analysis of a Loss of Alternating-Current Power Without Rod Insertion for the NuScale Power Module—II: Sensitivity to Varying Initial Temperature

Peter Yarsky

Nuclear Technology / Volume 207 / Number 5 / May 2021 / Pages 665-679

Technical Paper / dx.doi.org/10.1080/00295450.2020.1810465

Integral Effect Test and MARS-KS Calculation with Uncertainty Propagation Analysis for Direct Vessel Injection Line Break Intermediate-Break Loss-of-Coolant Accident

Byoung-Uhn Bae, Jae-Bong Lee, Yu-Sun Park, Jong-Rok Kim, Seok Cho, Kyoung-Ho Kang

Nuclear Technology / Volume 207 / Number 5 / May 2021 / Pages 680-691

Technical Paper / dx.doi.org/10.1080/00295450.2020.1796078

Enhancing the One-Dimensional SFR Thermal Stratification Model via Advanced Inverse Uncertainty Quantification Methods

Cihang Lu, Zeyun Wu, Xu Wu

Nuclear Technology / Volume 207 / Number 5 / May 2021 / Pages 692-710

Technical Paper / dx.doi.org/10.1080/00295450.2020.1805259

A Radiation-Tolerant Wireless Communication System for Severe Accident Monitoring Without Relying on Rad-Hardened Electronic Components

Qiang Huang, Jin Jiang

Nuclear Technology / Volume 207 / Number 5 / May 2021 / Pages 711-725

Technical Paper / dx.doi.org/10.1080/00295450.2020.1794436

Sampling and Analysis of PWR Primary Cooling System Corrosion Products Using an EPMA

Yang Hong Jung, Boung Ok Yoo

Nuclear Technology / Volume 207 / Number 5 / May 2021 / Pages 726-734

Technical Paper / dx.doi.org/10.1080/00295450.2020.1805250

Application of Flaw Updating Process on Probabilistic Integrity Analysis for a Reactor Pressure Vessel Subjected to Pressurized Thermal Shocks

Hsoung-Wei Chou, Pin-Chiun Huang, Yuh-Ming Ferng

Nuclear Technology / Volume 207 / Number 5 / May 2021 / Pages 735-749

Technical Paper / dx.doi.org/10.1080/00295450.2020.1796091

A Versatile Remediation Module for Remote Repair of Spent Nuclear Fuel and High-Level Waste Storage Containers

Stylianos Chatzidakis, Dominic Giuliano, Jeremy Slade, Wei Tang, Roger Miller, Steve Reeves, John Scaglione, Robert Howard

Nuclear Technology / Volume 207 / Number 5 / May 2021 / Pages 750-760

Technical Paper / dx.doi.org/10.1080/00295450.2020.1800309

Simulation of the Fast Reactor Fuel Assembly Duct-Bowing Reactivity Effect Using Monte Carlo Neutron Transport and Finite Element Analysis

Edward Lum, Chad L. Pope

Nuclear Technology / Volume 207 / Number 5 / May 2021 / Pages 761-770

Technical Paper / dx.doi.org/10.1080/00295450.2020.1794190

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