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Volume 208

Number 2

Development of Subchannel Void Sensor for Wide Pressure and Temperature Ranges and Its Application to Boiling Flow Dynamics in a Heated Rod Bundle

Takahiro Arai, Masahiro Furuya, Kenetsu Shirakawa

Nuclear Technology / Volume 208 / Number 2 / February 2022 / Pages 203-221

Technical Paper / dx.doi.org/10.1080/00295450.2021.1897733

Investigating the Heat Transfer Characteristics of Impinging Flow on a Downward-Facing Surface

Yuan Gao, Huai-En Hsieh, Huifang Miao, Zhe Zhou, Zhibo Zhang

Nuclear Technology / Volume 208 / Number 2 / February 2022 / Pages 222-231

Technical Paper / dx.doi.org/10.1080/00295450.2021.1899552

Nuclear Reactor Transient Diagnostics Using Classification and AutoML

Pedro Mena, R. A. Borrelli, Leslie Kerby

Nuclear Technology / Volume 208 / Number 2 / February 2022 / Pages 232-245

Technical Paper / dx.doi.org/10.1080/00295450.2021.1905470

PHWR Reactivity Device Incremental Macroscopic Cross Sections and Reactivities for a Molybdenum-Producing Bundle and a Standard Bundle

J. Haroon, E. Nichita

Nuclear Technology / Volume 208 / Number 2 / February 2022 / Pages 246-267

Technical Paper / dx.doi.org/10.1080/00295450.2021.1929768

Development of the Penetration Tube Failure Analysis Program in the Lower Head of the Reactor Vessel During a Severe Accident

J. Jung, H. Y. Kim, S. M. An

Nuclear Technology / Volume 208 / Number 2 / February 2022 / Pages 268-283

Technical Paper / dx.doi.org/10.1080/00295450.2021.1929769

Experimental Study of a System for Hydrogen Permeation from Gas Phase to Liquid Sodium

Pietro Brazzale, Aurélien Chassery, Thierry Gilardi, Christian Latgé, Xuân-Mi Meyer, Xavier Joulia

Nuclear Technology / Volume 208 / Number 2 / February 2022 / Pages 284-294

Technical Paper / dx.doi.org/10.1080/00295450.2021.1895661

Experimental Method for Verification of Calculated 137Cs Content in Nuclear Fuel Assemblies

Martin Bengtsson, Peter Jansson, Ulrika Bäckström, Fredrik Johansson, Anders Sjöland

Nuclear Technology / Volume 208 / Number 2 / February 2022 / Pages 295-302

Technical Paper / dx.doi.org/10.1080/00295450.2021.1880851

In-Canal Assay of High Specific Activity 60Co at the Advanced Test Reactor

Michael A. Reichenberger, Jagoda M. Urban-Klaehn, Jason V. Brookman, Joshua L. Peterson-Droogh, Jorge Navarro, Richard H. Howard

Nuclear Technology / Volume 208 / Number 2 / February 2022 / Pages 303-309

Technical Paper / dx.doi.org/10.1080/00295450.2021.1903299

Deliquescence of Eutectic LiCl-KCl Diluted with NaCl for Interim Waste Salt Storage

Levi Gardner, Allison Harward, Jerry Howard, Guy Fredrickson, Tae-Sic Yoo, Michael Simpson, Krista Carlson

Nuclear Technology / Volume 208 / Number 2 / February 2022 / Pages 310-317

Technical Paper / dx.doi.org/10.1080/00295450.2021.1889923

Toxicity Reduction with Total Volume Control in Nuclear Waste

Yuji Fukaya, Shohei Ueta, Tomohiko Yamamoto, Yoshitaka Chikazawa, Xing L. Yan

Nuclear Technology / Volume 208 / Number 2 / February 2022 / Pages 335-346

Technical Paper / dx.doi.org/10.1080/00295450.2021.1901001

Hydrogen Generation from α Radiolysis of Organic Materials in Transuranic Waste. Comparison Between Experimental Data and STORAGE Calculations

S. Esnouf, A. Dannoux-Papin, E. Bossé, V. Roux-Serret, C. Chapuzet, F. Cochin, J. Blancher

Nuclear Technology / Volume 208 / Number 2 / February 2022 / Pages 347-356

Technical Paper / dx.doi.org/10.1080/00295450.2021.1896927

Shield Design of the First Protective Collimator in the METU-Defocusing Beamline (DBL) Project

Selcen Uzun Duran, Pelin Uslu Kiçeci, Bilge Demirköz

Nuclear Technology / Volume 208 / Number 2 / February 2022 / Pages 364-370

Technical Paper / dx.doi.org/10.1080/00295450.2021.1888617

Core Modeling and Simulation of Peach Bottom 2 Turbine Trip Test 2 Using CASMO5/TRACE/PARCS

Shigeki Shiba, Tomohiro Sakai

Nuclear Technology / Volume 208 / Number 2 / February 2022 / Pages 371-383

Technical Note / dx.doi.org/10.1080/00295450.2021.1913032

Analysis of a Radioactive Corrosion Material Collected from Control Rod Drive Mechanism Housing of a PWR Using an EPMA

Yang Hong Jung, Young Jun Kim, Hyo Jik Lee

Nuclear Technology / Volume 208 / Number 2 / February 2022 / Pages 384-393

Technical Note / dx.doi.org/10.1080/00295450.2021.1893087

Influence of the Transients and Water Chemistry Parameters on Corrosion Product Behavior in the Primary System of Naval Reactor Plants

B. A. Gusev, A. A. Efimov, A. A. Zmitrodan, I. S. Orlenkov, S. N. Orlov, V. N. Panchuk

Nuclear Technology / Volume 208 / Number 2 / February 2022 / Pages 394-402

Technical Note / dx.doi.org/10.1080/00295450.2021.1893086