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Volume 203

Number 1 | Number 2 | Number 3

Number 1

Model Development for Risk-Based Safety Assessment of a Geological Disposal System of Radioactive Wastes Generated by Pyroprocessing of Pressurized Water Reactor Spent Fuel in Korea

Jung-Woo Kim, Dong-Keun Cho, Nak-Youl Ko, Jongtae Jeong, Min-Hoon Baik

Nuclear Technology / Volume 203 / Number 1 / July 2018 / Pages 1-16

Technical Paper / dx.doi.org/10.1080/00295450.2018.1426331

Numerical Modeling and Experimental Validation of Melt Pool Coolability Under Bottom Flooding with Decay Heat Simulation

Nitendra Singh, Arun K. Nayak, Parimal P. Kulkarni

Nuclear Technology / Volume 203 / Number 1 / July 2018 / Pages 17-33

Technical Paper / dx.doi.org/10.1080/00295450.2018.1426961

Using the Time-Correlated Induced Fission Method to Simultaneously Measure the 235U Content and the Burnable Poison Content in LWR Fuel Assemblies

M. A. Root, H. O. Menlove, R. C. Lanza, C. D. Rael, K. A. Miller, J. B. Marlow, J. G. Wendelberger

Nuclear Technology / Volume 203 / Number 1 / July 2018 / Pages 34-47

Technical Paper / dx.doi.org/10.1080/00295450.2018.1429112

Development of the Tritium Transport Analysis Code for the Thorium-Based Molten Salt Reactor

Youshi Zeng, Shengwei Wu, Wei Liu, Guanghua Wang, Nan Qian, Xiaoling Wu, Wenguan Liu, Yu Huang, Yuan Qian

Nuclear Technology / Volume 203 / Number 1 / July 2018 / Pages 48-57

Technical Paper / dx.doi.org/10.1080/00295450.2018.1433408

Verification of Modelica-Based Models with Analytical Solutions for Tritium Diffusion

Jordan D. Rader, M. Scott Greenwood, Paul W. Humrickhouse

Nuclear Technology / Volume 203 / Number 1 / July 2018 / Pages 58-65

Technical Paper / dx.doi.org/10.1080/00295450.2018.1431505

A Scoping Study of the Chemical Behavior of Cesium Iodide in the Presence of Boron in the Condensed Phase (650°C and 400°C) Under Primary Circuit Conditions

Mélany Gouëllo, Jouni Hokkinen, Teemu Kärkelä, Ari Auvinen

Nuclear Technology / Volume 203 / Number 1 / July 2018 / Pages 66-84

Technical Paper / dx.doi.org/10.1080/00295450.2018.1429111

Assessment of Parameters of Radioactive Aerosol Release Through Air Duct System Using the SOCRAT/V3 Code

R. V. Arutyunyan, D. A. Pripachkin, K. S. Dolganov, S. V. Tsaun, S. N. Krasnoperov, D. V. Aron, D. Yu. Tomashchik, E. L. Serebryakov, S. V. Panchenko, A. V. Shikin

Nuclear Technology / Volume 203 / Number 1 / July 2018 / Pages 92-100

Technical Paper / dx.doi.org/10.1080/00295450.2018.1432839

Treatment of Radioactive Wastewater from High-Temperature Gas-Cooled Reactor by Membrane System

Junfeng Li, Shuting Zhuang, Liang Wang, Jianlong Wang

Nuclear Technology / Volume 203 / Number 1 / July 2018 / Pages 101-107

Technical Note / dx.doi.org/10.1080/00295450.2018.1432838

Number 2

Experimentally Known Properties of U-10Zr Alloys: A Critical Review

Dawn E. Janney, Steven L. Hayes

Nuclear Technology / Volume 203 / Number 2 / August 2018 / Pages 109-128

Critical Review / dx.doi.org/10.1080/00295450.2018.1435137

Safety Analysis of a 300-MW(electric) Offshore Floating Nuclear Power Plant in Marine Environment

Yaoli Zhang, Jacopo Buongiorno, Michael Golay, Neil Todreas

Nuclear Technology / Volume 203 / Number 2 / August 2018 / Pages 129-145

Technical Paper / dx.doi.org/10.1080/00295450.2018.1433935

Simulations of Pressure-Tube–Heavy-Water Reactor Cores Fueled with Thorium-Based Mixed-Oxide Fuels

Ashlea V. Colton, Blair P. Bromley

Nuclear Technology / Volume 203 / Number 2 / August 2018 / Pages 146-172

Technical Paper / dx.doi.org/10.1080/00295450.2018.1444898

Steady-State Subchannel Thermal-Hydraulic Assessment of Proposed Thorium Fuel Designs

A. Nava Dominguez, Y. F. Rao

Nuclear Technology / Volume 203 / Number 2 / August 2018 / Pages 173-193

Technical Paper / dx.doi.org/10.1080/00295450.2018.1442085

Numerical Study of Integral Inherently Safe Light Water Reactor in Case of Inadvertent DHR Operation Based on the Multiscale Method

Mingjun Wang, Annalisa Manera, Victor Petrov, Suizheng Qiu, Wenxi Tian, G. H. Su

Nuclear Technology / Volume 203 / Number 2 / August 2018 / Pages 194-204

Technical Paper / dx.doi.org/10.1080/00295450.2018.1446656

Preliminary Waste Characterization Measurements in FiR 1 TRIGA Research Reactor Decommissioning Project

Antti Räty, Tommi Kekki, Merja Tanhua-Tyrkkö, Tiina Lavonen, Emmi Myllykylä

Nuclear Technology / Volume 203 / Number 2 / August 2018 / Pages 205-220

Technical Paper / dx.doi.org/10.1080/00295450.2018.1445402

Number 3

Seismic Probabilistic Risk Analysis and Application in a Nuclear Power Plant

Jinkai Wang, Modi Lin

Nuclear Technology / Volume 203 / Number 3 / September 2018 / Pages 221-231

Technical Paper / dx.doi.org/10.1080/00295450.2018.1448671

Resource Demand and Economic Impact of Various Thorium-Based Fuels for Potential Near-Term Use in a Pressure-Tube Heavy Water Reactor

Alberto D. Mendoza España, Daniel Wojtaszek, Ashlea V. Colton, Blair P. Bromley

Nuclear Technology / Volume 203 / Number 3 / September 2018 / Pages 232-243

Technical Paper / dx.doi.org/10.1080/00295450.2018.1447209

Development of a Validation Approach for an Integrated Waste Glass Melter Model

Donna Post Guillen, Alexander W. Abboud, Richard Pokorny, William C. Eaton, Derek Dixon, Kevin Fox, Albert A. Kruger

Nuclear Technology / Volume 203 / Number 3 / September 2018 / Pages 244-260

Technical Paper / dx.doi.org/10.1080/00295450.2018.1458559

Parameter Surveys on Glass-Bonded Sodalite Synthesis Conditions from Spent Salt Generated in Pyroprocess

Koichi Uozumi, Kenji Fujihata, Takeshi Tsukada

Nuclear Technology / Volume 203 / Number 3 / September 2018 / Pages 261-271

Technical Paper / dx.doi.org/10.1080/00295450.2018.1454807

Phase Equilibria Studies of the LiCl-KCl-UCl3 System

Amber L. Hames, Alena Paulenova, James L. Willit, Mark A. Williamson

Nuclear Technology / Volume 203 / Number 3 / September 2018 / Pages 272-281

Technical Paper / dx.doi.org/10.1080/00295450.2018.1448673

Mechanical Property Degradation of Unirradiated Zircaloy-4 Cladding After Creep Deformation

Jong-Dae Hong, Euijung Kim, Yong-Sik Yang, Dong-Hak Kook

Nuclear Technology / Volume 203 / Number 3 / September 2018 / Pages 282-292

Technical Paper / dx.doi.org/10.1080/00295450.2018.1448203

Unsteady Single-Phase Natural-Circulation Flow Mixing Prediction Using 3-D Thermal-Hydraulic System and CFD Codes

A. Bousbia Salah, S. C. Ceuca, R. Puragliesi, R. Mukin, A. Grahn, S. Kliem, J. Vlassenbroeck, H. Austregesilo

Nuclear Technology / Volume 203 / Number 3 / September 2018 / Pages 293-314

Technical Paper / dx.doi.org/10.1080/00295450.2018.1461517

Vibration Effect Induced by Acoustic Pressure for UDV Measurement in Small Flow Channel

Shaoqiu Huang, Zhiqiang Zhu, Wangli Huang, Jian He, Jie Yu

Nuclear Technology / Volume 203 / Number 3 / September 2018 / Pages 315-324

Technical Paper / dx.doi.org/10.1080/00295450.2018.1460126

A Methodology for Determining the Concentration of Naturally Occurring Radioactive Materials in an Urban Environment

Mathew W. Swinney, Douglas E. Peplow, Bruce W. Patton, Andrew D. Nicholson, Daniel E. Archer, Michael J. Willis

Nuclear Technology / Volume 203 / Number 3 / September 2018 / Pages 325-335

Technical Paper / dx.doi.org/10.1080/00295450.2018.1458558

Adhesion Force Measurements: Graphite Cluster Interacting with VHTR Steel

Naphtali M. Mokgalapa, Tushar K. Ghosh, Robert V. Tompson, Sudarshan K. Loyalka

Nuclear Technology / Volume 203 / Number 3 / September 2018 / Pages 336-347

Technical Note / dx.doi.org/10.1080/00295450.2018.1453729

 
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