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Volume 182

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Number 1

Gaussian Processes for State Identification in Pressurized Water Reactors

Andreas Ikonomopoulos, Miltiadis Alamaniotis, Stylianos Chatzidakis, Lefteri H. Tsoukalas

Nuclear Technology / Volume 182 / Number 1 / April 2013 / Pages 1-12

Technical Paper / Fission Reactors

Assessment of the Efficiency of Extended Power Uprates at U.S. Boiling Water Reactors

Brenden Heidrich, Samuel A. Oyewole, Richard Olawoyin

Nuclear Technology / Volume 182 / Number 1 / April 2013 / Pages 13-25

Technical Paper / Fission Reactors/Nuclear Plant Operations and Control

Salt-Cooled Modular Innovative Thorium Heavy Water-Moderated Reactor System

Holly R. Trellue, Richard J. Kapernick, D. V. Rao, J. Zhang, Jack D. Galloway

Nuclear Technology / Volume 182 / Number 1 / April 2013 / Pages 26-38

Technical Paper / Fission Reactors/Fuel Cycle and Management

Viability Assessment of Noble Gas Bundle Tagging for Failed-Fuel Identification in CANDU Reactors

B. Pollack, B. J. Lewis, D. Kelly

Nuclear Technology / Volume 182 / Number 1 / April 2013 / Pages 39-48

Technical Paper / Fission Reactors/Fuel Cycle and Management

The Effect of Coating Parameters and Annealing on the Crushing Strength of TRISO Coated Particles

J. J. Hancke, G. T. Van Rooyen, J. P. R. De Villiers

Nuclear Technology / Volume 182 / Number 1 / April 2013 / Pages 49-56

Technical Paper / Fission Reactors/Fuel Cycle and Management

The Role of Gd2O3 Phase Transition on UO2-Gd2O3 Fuel Sintering

Michelangelo Durazzo, Ricardo Mendes Leal Neto, Adonis Marcelo Saliba-Silva, Elita Fontenele Urano de Carvalho, Humberto Gracher Riella

Nuclear Technology / Volume 182 / Number 1 / April 2013 / Pages 57-62

Technical Paper / Fuel Cycle and Management/Miscellaneous

Hybrid Monte Carlo/Deterministic Methods for Accelerating Active Interrogation Modeling

Douglas E. Peplow, Thomas M. Miller, Bruce W. Patton, John C. Wagner

Nuclear Technology / Volume 182 / Number 1 / April 2013 / Pages 63-74

Technical Paper / Radiation Transport and Protection

Updating of Analytical Model to Consider Aging Effects of Lead-Rubber Bearings for the Seismic Design of Base-Isolated Nuclear Power Plants

Thuy Dung Vu, Dookie Kim, Sung Gook Cho

Nuclear Technology / Volume 182 / Number 1 / April 2013 / Pages 75-83

Technical Paper / Nuclear Plant Operations and Control/Miscellaneous

Single-Stage Dual-Column HPLC Technique for Separation and Determination of Lanthanides in Uranium Matrix: Application to Burnup Measurement on Nuclear Reactor Fuel

Arpita Datta, N. Sivaraman, T. G. Srinivasan, P. R. Vasudeva Rao

Nuclear Technology / Volume 182 / Number 1 / April 2013 / Pages 84-97

Technical Paper / Reprocessing

Modeling the Anodic Behavior of U, Zr, and U-Zr Alloy in Molten LiCl-KCl Eutectic

Aligati Venkatesh, Suddhasattwa Ghosh, S. Vandarkuzhali, B. Prabhakara Reddy, K. Nagarajan, P. R. Vasudeva Rao

Nuclear Technology / Volume 182 / Number 1 / April 2013 / Pages 98-110

Technical Paper / Reprocessing

Long-Term Electrochemical Criteria for Crevice Corrosion in Concentrated Chloride Solutions

T. Ahn, H. Jung, P. Shukla, X. He

Nuclear Technology / Volume 182 / Number 1 / April 2013 / Pages 111-122

Technical Paper / Materials for Nuclear Systems

Number 2

Foreword: Special Issue on the Symposium on Radiation Effects in Ceramic Oxide and Novel LWR Fuels

Peng Xu, Todd R. Allen

Nuclear Technology / Volume 182 / Number 2 / May 2013 / Page 123

Simulation of Pellet-Cladding Interaction with the PLEIADES Fuel Performance Software Environment

B. Michel, C. Nonon, J. Sercombe, F. Michel, V. Marelle

Nuclear Technology / Volume 182 / Number 2 / May 2013 / Pages 124-137

Technical Paper / Special Issue on the Symposium on Radiation Effects in Ceramic Oxide and Novel LWR Fuels / Fuel Cycle and Management

On the Response of Ionic Crystals to Irradiation

Dilpuneet Aidhy, Dieter Wolf

Nuclear Technology / Volume 182 / Number 2 / May 2013 / Pages 138-144

Technical Paper / Special Issue on the Symposium on Radiation Effects in Ceramic Oxide and Novel LWR Fuels / Fuel Cycle and Management

Three-Dimensional Characterization of Sintered UO2+x: Effects of Oxygen Content on Microstructure and Its Evolution

Karin Rudman, Patricia Dickerson, Darrin Byler, Robert McDonald, Harn Lim, Pedro Peralta, Chris Stanek, Kenneth McClellan

Nuclear Technology / Volume 182 / Number 2 / May 2013 / Pages 145-154

Technical Paper / Special Issue on the Symposium on Radiation Effects in Ceramic Oxide and Novel LWR Fuels / Fuel Cycle and Management

Microstructurally Explicit Simulation of Intergranular Mass Transport in Oxide Nuclear Fuels

Harn Chyi Lim, Karin Rudman, Kapil Krishnan, Robert McDonald, Patricia Dickerson, Darrin Byler, Pedro Peralta, Chris Stanek, Kenneth McClellan

Nuclear Technology / Volume 182 / Number 2 / May 2013 / Pages 155-163

Technical Paper / Special Issue on the Symposium on Radiation Effects in Ceramic Oxide and Novel LWR Fuels / Fuel Cycle and Management

Transmission Electron Microscopy Investigation of Krypton Bubbles in Polycrystalline CeO2

Lingfeng He, Clarissa Yablinsky, Mahima Gupta, Jian Gan, Marquis A. Kirk, Todd R. Allen

Nuclear Technology / Volume 182 / Number 2 / May 2013 / Pages 164-169

Technical Paper / Special Issue on the Symposium on Radiation Effects in Ceramic Oxide and Novel LWR Fuels / Materials for Nuclear Systems

R&D in Support of ASTRID and JSFR: Cross-Analysis and Identification of Possible Areas of Cooperation

Nicolas Devictor, Yoshitaka Chikazawa, Manuel Saez, Gilles Rodriguez, Hiroki Hayafune

Nuclear Technology / Volume 182 / Number 2 / May 2013 / Pages 170-186

Regular Technical Paper / Special Issue on the Symposium on Radiation Effects in Ceramic Oxide and Novel LWR Fuels / Fission Reactors

Introduction of Thorium-Based Fuels in High Conversion Pressurized Water Reactors

V. Vallet, B. Gastaldi, J. Politello, A. Santamarina, L. Van Den Durpel

Nuclear Technology / Volume 182 / Number 2 / May 2013 / Pages 187-206

Regular Technical Paper / Special Issue on the Symposium on Radiation Effects in Ceramic Oxide and Novel LWR Fuels / Fission Reactors

Determining Optimal Neutron Spectra for Transmutation and Isotope Management

Mark Massie, Benoit Forget

Nuclear Technology / Volume 182 / Number 2 / May 2013 / Pages 207-223

Regular Technical Paper / Special Issue on the Symposium on Radiation Effects in Ceramic Oxide and Novel LWR Fuels / Fission Reactors

Effects of Source and Geometry Modeling on the Shielding Calculations for a Spent Nuclear Fuel Dry Storage Cask

Y. F. Chen, Y. F. Chiou, S. J. Chang, S. H. Jiang, R. J. Sheu

Nuclear Technology / Volume 182 / Number 2 / May 2013 / Pages 224-234

Regular Technical Paper / Special Issue on the Symposium on Radiation Effects in Ceramic Oxide and Novel LWR Fuels / Radiation Transport and Protection

Study on UF-2 Extraction in Accelerator Mass Spectrometry Measurement of 236U

Xianggao Wang, Kejun Dong, Ming He, Shaoyong Wu, Shan Jiang

Nuclear Technology / Volume 182 / Number 2 / May 2013 / Pages 235-241

Regular Technical Paper / Special Issue on the Symposium on Radiation Effects in Ceramic Oxide and Novel LWR Fuels / Reprocessing

Laser-Assisted Decontamination of Fuel Pins for Prototype Fast Breeder Reactor

Aniruddha Kumar, R. B. Bhatt, Mohd. Afzal, J. P. Panakkal, Dhruba J. Biswas, J. Padma Nilaya, A. K. Das

Nuclear Technology / Volume 182 / Number 2 / May 2013 / Pages 242-247

Regular Technical Paper / Special Issue on the Symposium on Radiation Effects in Ceramic Oxide and Novel LWR Fuels / Decontamination/Decommissioning

Number 3

Detection of Simulated Steam Leak into Sodium in Steam Generator of PFBR by Argon Injection Using Signal Analysis Techniques

P. Kalyanasundaram, Baldev Raj, V. Prakash, Ramakrishna Ranga

Nuclear Technology / Volume 182 / Number 3 / June 2013 / Pages 249-258

Technical Paper / Fission Reactors/Nuclear Plant Operations and Control

Experimental Investigation of Hydraulics and Lateral Mixing for Helical-Cruciform Fuel Rod Assemblies

T. M. Conboy, T. J. McKrell, M. S. Kazimi

Nuclear Technology / Volume 182 / Number 3 / June 2013 / Pages 259-273

Technical Paper / Fuel Cycle and Management/Thermal Hydraulics

Transmutation Fuel Cycle Analyses of the SABR Fission-Fusion Hybrid Burner Reactor for Transuranic and Minor Actinide Fuels

C. M. Sommer, W. M. Stacey, B. Petrovic, C. L. Stewart

Nuclear Technology / Volume 182 / Number 3 / June 2013 / Pages 274-285

Technical Paper / Fuel Cycle and Management

A Study of Nanoparticle Surface Modification Effects on Pool Boiling Critical Heat Flux

G. Stange, H. Yeom, B. Semerau, K. Sridharan, M. Corradini

Nuclear Technology / Volume 182 / Number 3 / June 2013 / Pages 286-301

Technical Paper / Thermal Hydraulics

The Triggerability and Explosion Potentials of Reactor Core Melt at Fuel Coolant Interactions

I. K. Park, J. H. Kim, S. H. Hong, S. W. Hong

Nuclear Technology / Volume 182 / Number 3 / June 2013 / Pages 302-314

Technical Paper / Thermal Hydraulics

Thermal-Hydraulic Analysis for HEU and LEU Transitional Core Conversion of the MIT Research Reactor

Sung Joong Kim, Lin-Wen Hu, Floyd Dunn

Nuclear Technology / Volume 182 / Number 3 / June 2013 / Pages 315-334

Technical Paper / Thermal Hydraulics

Comparison of Measured and Monte Carlo Results for Neutron Beam Transmission Through an Irradiated Nuclear Fuel Assembly

Chad L. Pope, Michael J. Lineberry

Nuclear Technology / Volume 182 / Number 3 / June 2013 / Pages 335-348

Technical Paper / Radiation Transport and Protection/Radioisotopes

Application of Zirconium Alloys for Reprocessing Plant Components

U. Kamachi Mudali, A. Ravi Shankar, R. Natarajan, N. Saibaba, Baldev Raj

Nuclear Technology / Volume 182 / Number 3 / June 2013 / Pages 349-357

Technical Paper / Reprocessing/Materials for Nuclear Systems

Intelligent Radioactive Waste Management Platform for Radioactive Waste Storage Facilities

Y.-C. Chen, Y.-S. Yu, R.-S. Chen, I-Hsin Chou, H. M. Sun, K. C. Yeh

Nuclear Technology / Volume 182 / Number 3 / June 2013 / Pages 358-368

Technical Paper / Radioactive Waste Management and Disposal

Analysis of Measurement Uncertainty of Material Unaccounted for in the Reference Pyroprocessing Facility

Bo-Young Han, Hee-Sung Shin, Ho-Dong Kim

Nuclear Technology / Volume 182 / Number 3 / June 2013 / Pages 369-377

Technical Note / Fuel Cycle and Management

 
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