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Volume 196

Number 1

Full-Core Evaluation of Uranium-Based Fuels Augmented with Small Amounts of Thorium in Pressure Tube Heavy Water Reactors

Ashlea V. Colton, Blair P. Bromley

Nuclear Technology / Volume 196 / Number 1 / October 2016 / Pages 1-12

Technical Paper / dx.doi.org/10.13182/NT16-70

Basis for Fluoride Salt–Cooled High-Temperature Reactors with Nuclear Air-Brayton Combined Cycles and Firebrick Resistance-Heated Energy Storage

Charles Forsberg, Per F. Peterson

Nuclear Technology / Volume 196 / Number 1 / October 2016 / Pages 13-33

Technical Paper / dx.doi.org/10.13182/NT16-28

Thermal-Hydraulic Analyses of Transportable Fluoride Salt–Cooled High-Temperature Reactor with CFD Modeling

Chenglong Wang, Kaichao Sun, Lin-Wen Hu, Suizheng Qiu, G. H. Su

Nuclear Technology / Volume 196 / Number 1 / October 2016 / Pages 34-52

Technical Paper / dx.doi.org/10.13182/NT15-42

Radiation Heat Transfer in the Molten Salt FLiNaK

Ethan S. Chaleff, Thomas Blue, Piyush Sabharwall

Nuclear Technology / Volume 196 / Number 1 / October 2016 / Pages 53-60

Technical Paper / dx.doi.org/10.13182/NT16-52

Secondary Sodium Fire Measures in JSFR

Yoshitaka Chikazawa, Atsushi Katoh, Tomohiko Yamamoto, Shigenobu Kubo, Shuji Ohno, Mikinori Iwasaki, Hiroyuki Hara, Yoshio Shimakawa, Hiroshi Sakaba

Nuclear Technology / Volume 196 / Number 1 / October 2016 / Pages 61-73

Technical Paper / dx.doi.org/10.13182/NT15-131

Capability Enhancement of MATRIX Electromagnetic Pump Analysis Code by Including Thermal Analysis

Ana Da Silva, Pradip Saha, Eric P. Loewen

Nuclear Technology / Volume 196 / Number 1 / October 2016 / Pages 74-88

Technical Paper / dx.doi.org/10.13182/NT16-55

Corrosion Properties of Zircaloy-4 and M5 Under Simulated PWR Water Conditions

Akira Shibata, Yoshiaki Kato, Taketoshi Taguchi, Masatoshi Futakawa, Katsuhiro Maekawa

Nuclear Technology / Volume 196 / Number 1 / October 2016 / Pages 89-99

Technical Paper / dx.doi.org/10.13182/NT16-54

High-Temperature Corrosion Testing of Uranium Silicide Surrogates

K. Urso, K. Sridharan, B. J. Jaques, G. Alanko, D. P. Butt, M. Meyer, P. Xu, B. Tyburska-Püschel

Nuclear Technology / Volume 196 / Number 1 / October 2016 / Pages 100-110

Technical Paper / dx.doi.org/10.13182/NT15-155

Sample Preparation Techniques for Grain Boundary Characterization of Annealed TRISO-Coated Particles

M. L. Dunzik-Gougar, I. J. van Rooyen, C. M. Hill, T. Trowbridge, J. Madden, J. Burns

Nuclear Technology / Volume 196 / Number 1 / October 2016 / Pages 111-120

Technical Paper / dx.doi.org/10.13182/NT15-129

Diffusion and Sorption Properties of Some Sorbing Nuclides onto Granodiorite in a Modified Through-Diffusion Setup

Chung-Kyun Park, Min-Hoon Baik, Yong-Kwon Koh

Nuclear Technology / Volume 196 / Number 1 / October 2016 / Pages 121-129

Technical Paper / dx.doi.org/10.13182/NT15-148

Creep Evaluation of Traditional and Nuclear Power Plant High-Temperature Components, Using Small Pin-Loaded One-Bar and Two-Bar Specimens

Balhassn S. M. Ali, Terry Y. P. Yuen, Mohamed Saber

Nuclear Technology / Volume 196 / Number 1 / October 2016 / Pages 130-140

Technical Paper / dx.doi.org/10.13182/NT15-117

 

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