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Volume 203

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

 
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