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Volume 189

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Number 1

Evaluation of the Fluid-Structure Interaction Effects in a Lead-Cooled Fast Reactor

R. Lo Frano

Nuclear Technology / Volume 189 / Number 1 / January 2015 / Pages 1-10

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT14-23

Modeling and SISO/MIMO Control with an Inverse Nyquist Array and Stability Analysis for Load-Follow Operation of PWR Core Without Boron

Gang Li

Nuclear Technology / Volume 189 / Number 1 / January 2015 / Pages 11-29

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT13-115

Evaluation of External Event Effects on JSFR Fuel Handling System

Atsushi Katoh, Yoshitaka Chikazawa, Masayuki Uzawa, Fumiaki Kaneko, Akihiro Ide

Nuclear Technology / Volume 189 / Number 1 / January 2015 / Pages 30-44

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT13-147

Measurements of Charged Aerosol Coagulation

Matthew P. Simones, Sudarshan K. Loyalka

Nuclear Technology / Volume 189 / Number 1 / January 2015 / Pages 45-62

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT14-14

Implications of Plutonium Isotopic Separation on Closed Fuel Cycles and Repository Design

Charles Forsberg

Nuclear Technology / Volume 189 / Number 1 / January 2015 / Pages 63-70

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT13-137

Analysis of Loss-of-Flow Accidents for the NIST Research Reactor with Fuel Conversion from HEU to LEU

J. S. Baek, A. Cuadra, L.-Y. Cheng, A. L. Hanson, N. R. Brown, D. J. Diamond

Nuclear Technology / Volume 189 / Number 1 / January 2015 / Pages 71-86

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT13-124

Fault-Tolerant Architecture and Reliability Analysis for NISS-RPS

Dong Hoon Kim, Gwang Seop Son, Choul Woong Son, Dong Young Lee

Nuclear Technology / Volume 189 / Number 1 / January 2015 / Pages 87-102

Technical Paper / Nuclear Plant Operations and Control / dx.doi.org/10.13182/NT13-142

On the Solution of the Nonlinear Fractional Neutron Point-Kinetics Equation with Newtonian Temperature Feedback Reactivity

A. Patra, S. Saha Ray

Nuclear Technology / Volume 189 / Number 1 / January 2015 / Pages 103-109

Technical Note / Reactor Safety / dx.doi.org/10.13182/NT13-148

Number 2

Selector-Valve Failed Fuel Detection and Location System for Japan Sodium-Cooled Fast Reactor

Kosuke Aizawa, Kaoru Fujita, Hideki Kamide, Naoto Kasahara

Nuclear Technology / Volume 189 / Number 2 / February 2015 / Pages 111-121

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT13-156

The Behavior of Radiolytically Produced Hydrogen in a High-Level Liquid Waste Tank of a Reprocessing Plant: Hydrogen Concentration in the Ventilated Tank Air

Hiroshi Kinuhata, Yoji Shirato, Masahiro Tomiyama, Takashi Kodama, Masanao Nakano, Takeshi Yasuda, Koichi Tsutagi, Yasuyuki Yoshino, Yoshinobu Nakamura, Yoshikazu Tamauchi, Shingo Matsuoka

Nuclear Technology / Volume 189 / Number 2 / February 2015 / Pages 122-132

Technical Paper / Reprocessing / dx.doi.org/10.13182/NT14-11

Experimental Investigation of the Interaction Kinetics Between Metallic Melt and Special Concrete

S. M. An, K. S. Ha, B. T. Min, H. Y. Kim, J. H. Song

Nuclear Technology / Volume 189 / Number 2 / February 2015 / Pages 133-142

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT14-24

Tagging-Gas Failed Fuel Detection and Location System for Sodium-Cooled Reactors

Kosuke Aizawa, Yoshitaka Chikazawa

Nuclear Technology / Volume 189 / Number 2 / February 2015 / Pages 143-151

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT13-161

Assessment of the Potential of By-Product Recovery of Thorium to Satisfy Demands of a Future Thorium Fuel Cycle

Timothy Ault, Steven Krahn, Allen Croff

Nuclear Technology / Volume 189 / Number 2 / February 2015 / Pages 152-162

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT14-19

Effect of Thermal Conductivity Degradation for High-Burnup Fuel During a Postulated Control Element Assembly Ejection Accident

Seok-Hee Ryu, Kil-Sup Um, Jae-Il Lee

Nuclear Technology / Volume 189 / Number 2 / February 2015 / Pages 163-172

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT14-28

Demonstration of Signature-Based Safeguards for Pyroprocessing as Applied to Electrorefining and the Ingot Casting Process

Philip L. Lafreniere, Devin S. Rappleye, Robert O. Hoover, Michael F. Simpson, Edward D. Blandford

Nuclear Technology / Volume 189 / Number 2 / February 2015 / Pages 173-185

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT14-35

Parametric Study of Trade-Offs in the Hybrid Transport Theory MAVRIC Methodology for Shielding and Dosimetry Analyses

Benjamin C. Bowers, Bojan Petrovic

Nuclear Technology / Volume 189 / Number 2 / February 2015 / Pages 186-201

Technical Note / Radiation Transport and Protection / dx.doi.org/10.13182/NT12-162

Reactor Physics Scoping and Characterization Study on Implementation of TRIGA Fuel in the Advanced Test Reactor

Jennifer A. Lyons, Wade R. Marcum, Sean Morrell, Mark DeHart

Nuclear Technology / Volume 189 / Number 2 / February 2015 / Pages 202-217

Technical Note / Fission Reactors / dx.doi.org/10.13182/NT14-33

Number 3

Representing Nuclear Criticality Excursion Experiment Data by an Artificial Neural Network

Peter L. Angelo

Nuclear Technology / Volume 189 / Number 3 / March 2015 / Pages 219-240

Technical Paper / Criticality Safety / dx.doi.org/10.13182/NT14-44

Generation of Graphite Particles by Sliding Abrasion and Their Characterization

Raymond S. Troy, Robert V. Tompson, Tushar K. Ghosh, Sudarshan K. Loyalka, Nidia C. Gallego

Nuclear Technology / Volume 189 / Number 3 / March 2015 / Pages 241-257

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT14-25

Influence of Carbon Nanotube Dispersion in UO2–Carbon Nanotube Ceramic Matrix Composites Utilizing Spark Plasma Sintering

Andrew Cartas, Haitang Wang, Ghatu Subhash, Ronald Baney, James Tulenko

Nuclear Technology / Volume 189 / Number 3 / March 2015 / Pages 258-267

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT14-7

Turbine Bypass, Mass Inventory, and Mixed-Mode Generator Power Control of S-CO2 Recompression Cycle

Alexander Heifetz, Richard Vilim

Nuclear Technology / Volume 189 / Number 3 / March 2015 / Pages 268-277

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT13-113

Conceptual Design of Passive Containment Cooling System for APR-1400 Using Multipod Heat Pipe

Gyeongho Nam, Junseok Park, Sangnyung Kim

Nuclear Technology / Volume 189 / Number 3 / March 2015 / Pages 278-293

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT13-121

Influence of Solution Chemistry on the Selective Adsorption of Uranium and Thorium Onto Activated Carbon

S. M. Yakout

Nuclear Technology / Volume 189 / Number 3 / March 2015 / Pages 294-300

Technical Paper / Reprocessing / dx.doi.org/10.13182/NT14-39

Microfluidic-Based Sample Chips for Radioactive Solutions

J. L. Tripp, J. D. Law, T. E. Smith, V. J. Rutledge, W. F. Bauer, R. D. Ball, P. A. Hahn

Nuclear Technology / Volume 189 / Number 3 / March 2015 / Pages 301-311

Technical Paper / Radioisotopes / dx.doi.org/10.13182/NT14-5

Radial Density Distribution in Irradiated FBR MOX Fuel Pellets

Akihiro Ishimi, Kozo Katsuyama, Hirofumi Nakamura, Takeo Asaga, Hirotaka Furuya

Nuclear Technology / Volume 189 / Number 3 / March 2015 / Pages 312-317

Technical Paper / Materials for Nuclear Systems / dx.doi.org/10.13182/NT14-34

 
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