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Volume 207

Number 2

Transition Core Analysis for HEU to LEU Fuel Conversion at the University of Missouri Research Reactor

Wilson Cowherd, John Stillman, John Gahl, Leslie Foyto, Erik Wilson

Nuclear Technology / Volume 207 / Number 2 / February 2021 / Pages 167-181

Technical Paper / dx.doi.org/10.1080/00295450.2020.1763720

Demand-Driven Deployment Capabilities in Cyclus, a Fuel Cycle Simulator

Gwendolyn J. Chee, Roberto E. Fairhurst Agosta, Jin Whan Bae, Robert R. Flanagan, Anthony M. Scopatz, Kathryn D. Huff

Nuclear Technology / Volume 207 / Number 2 / February 2021 / Pages 182-203

Technical Paper / dx.doi.org/10.1080/00295450.2020.1753444

Issues of Safety Assessment of New Russian NPP Projects in View of Current Requirements for the Probability of a Large Release

V. B. Morozov, A. E. Kiselev, A. A. Kiselev, K. S. Dolganov, D. Yu. Tomashchik, S. N. Krasnoperov

Nuclear Technology / Volume 207 / Number 2 / February 2021 / Pages 204-216

Technical Paper / dx.doi.org/10.1080/00295450.2020.1767998

Tellurium Behavior in the Containment Sump: Dissolution, Redox, and Radiolysis Effects

Anna-Elina Pasi, Henrik Glänneskog, Mark R. St.-J Foreman, Christian Ekberg

Nuclear Technology / Volume 207 / Number 2 / February 2021 / Pages 217-227

Technical Paper / dx.doi.org/10.1080/00295450.2020.1762456

Development of a Lumped Parameter Dynamic Degassing Model for Spray-Heating Degasser and Its Application in the Pressurizer of a Pressurized Water Reactor

Xianping Zhong, Jiyang Yu, Xiaolong Zhang, Muhammad Saeed, Yi Li, Zhihui Chen, Bin Tang, Yan Sun, Tao Huang

Nuclear Technology / Volume 207 / Number 2 / February 2021 / Pages 228-246

Technical Paper / dx.doi.org/10.1080/00295450.2020.1763097

Semianalytical Solution to Near-Field Temperature in Nuclear Waste Repository

Xiangyun Zhou, Annan Zhou, De’An Sun, Daichao Sheng

Nuclear Technology / Volume 207 / Number 2 / February 2021 / Pages 247-262

Technical Paper / dx.doi.org/10.1080/00295450.2020.1756161

Recovery of Zirconium from Zircaloys Using a Hydrochlorination Process

Rosendo Borjas Nevarez, Bruce McNamara, Frederic Poineau

Nuclear Technology / Volume 207 / Number 2 / February 2021 / Pages 263-269

Technical Paper / dx.doi.org/10.1080/00295450.2020.1757961

The PyNE-Based Burnup Analysis Method for Accelerator-Driven Subcritical Systems

Jin-Yang Li, Long Gu, Hu-Shan Xu, Yong Dai, You-Peng Zhang, Cun-Feng Yao, Rui Yu, Lu Zhang, Sheng Yang

Nuclear Technology / Volume 207 / Number 2 / February 2021 / Pages 270-284

Technical Paper / dx.doi.org/10.1080/00295450.2020.1757963

An Optimized Method for Bonner Sphere Spectrometer Design and Validation by Measuring 252Cf Spectra

Qingjun Zhu, Xianfang Meng, Wuhui Chen, Songlin Liu, Kai Huang

Nuclear Technology / Volume 207 / Number 2 / February 2021 / Pages 285-291

Technical Paper / dx.doi.org/10.1080/00295450.2020.1750250

Optimized Digital Sallen-Key Shaping Algorithm for Radiation Detector Signal Processing

Song Wengang, Zhang Lijun, Wang Guanying, Li Qiang

Nuclear Technology / Volume 207 / Number 2 / February 2021 / Pages 292-298

Technical Paper / dx.doi.org/10.1080/00295450.2020.1747838

Design and Optimization Based on Monte Carlo Method of a Range Shifter for Proton Therapy

Yecheng Yu, Ping Tan, Yinjie Lin, Yuying Hu, Huidong Guo, Hao Lei, Zhongqi Zhang, Jiadong Li, Delin Hu

Nuclear Technology / Volume 207 / Number 2 / February 2021 / Pages 299-315

Technical Paper / dx.doi.org/10.1080/00295450.2020.1747839

The Inventory and Source Term Simulation of the Argonaut Nuclear Reactor Inside a Severe Accident

Anderson M. S. Alves, Adino Heimlich, Fernando Lamego, Celso M. F. Lapa

Nuclear Technology / Volume 207 / Number 2 / February 2021 / Pages 316-322

Technical Note / dx.doi.org/10.1080/00295450.2020.1747840

 

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