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Volume 205

Number 7

Analysis of Velocity Distributions Across a Model Helical Coil Steam Generator

Michael S. Gorman, Marilyn Delgado, Saya Lee, Yassin A. Hassan

Nuclear Technology / Volume 205 / Number 7 / July 2019 / Pages 881-890

Technical Paper – Selected papers from the 2018 ANS Student Conference / dx.doi.org/10.1080/00295450.2019.1600998

Development of an Experimental Routine for Electrochemical and Laser-Induced Breakdown Spectroscopy Composition Measurements of SmCl3 in LiCl-KCl Eutectic Salt Systems

Hunter Andrews, Supathorn Phongikaroon

Nuclear Technology / Volume 205 / Number 7 / July 2019 / Pages 891-904

Technical Paper – Selected papers from the 2018 ANS Student Conference / dx.doi.org/10.1080/00295450.2018.1551988

Computer-Aided Star Shot Analysis for Linac Quality Assurance Testing

Gregory A. Szalkowski, Justin Roper

Nuclear Technology / Volume 205 / Number 7 / July 2019 / Pages 905-911

Technical Paper – Selected papers from the 2018 ANS Student Conference / dx.doi.org/10.1080/00295450.2018.1533349

GPT-Free Sensitivity Analysis for Monte Carlo Models

Zeyun Wu, Jingang Liang, Xingjie Peng, Hany S. Abdel-Khalik

Nuclear Technology / Volume 205 / Number 7 / July 2019 / Pages 912-927

Regular Technical Paper / dx.doi.org/10.1080/00295450.2018.1556062

Multigroup Cross-Section Generation with the OpenMC Monte Carlo Particle Transport Code

William Boyd, Adam Nelson, Paul K. Romano, Samuel Shaner, Benoit Forget, Kord Smith

Nuclear Technology / Volume 205 / Number 7 / July 2019 / Pages 928-944

Regular Technical Paper / dx.doi.org/10.1080/00295450.2019.1571828

Quantile Regressions Applied to Pressurized Water Reactor CHF Correlation Safety Criteria

Ross Pivovar, Ole Wieckhorst

Nuclear Technology / Volume 205 / Number 7 / July 2019 / Pages 945-950

Regular Technical Paper / dx.doi.org/10.1080/00295450.2018.1548220

Measurements of Total Hemispherical Emissivity of A508/A533B Alloy Steel

Faten N. Al Zubaidi, Kyle L. Walton, Robert V. Tompson, Tushar K. Ghosh, Sudarshan K. Loyalka

Nuclear Technology / Volume 205 / Number 7 / July 2019 / Pages 951-963

Regular Technical Paper / dx.doi.org/10.1080/00295450.2019.1573618

A Note on the Use of Uranine Tracer to Visualize Radionuclide Migration Experiments: Some Observations and Problems

Helen Winberg-Wang, Ivars Neretnieks, Mikko Voutilainen

Nuclear Technology / Volume 205 / Number 7 / July 2019 / Pages 964-977

Regular Technical Paper / dx.doi.org/10.1080/00295450.2019.1573620

Design and Optimization of a Fast Neutron Radiography System Based on a High-Intensity D-T Fusion Neutron Generator

Jie Wang, Yanan Li, Yongfeng Wang, Taosheng Li, Zaodi Zhang

Nuclear Technology / Volume 205 / Number 7 / July 2019 / Pages 978-986

Regular Technical Paper / dx.doi.org/10.1080/00295450.2019.1575122

MATLAB/FLUENT Model for Studying the Uncertainty Quantification of Spent Nuclear Fuel Heat Transfer

Imane Khalil, Quinn Pratt

Nuclear Technology / Volume 205 / Number 7 / July 2019 / Pages 987-991

Technical Note / dx.doi.org/10.1080/00295450.2018.1554026

Fission Gas Release from Irradiated UO2+x During Transient Annealing

A. R. Massih

Nuclear Technology / Volume 205 / Number 7 / July 2019 / Pages 992-1001

Technical Note / dx.doi.org/10.1080/00295450.2019.1568102

 
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