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Volume 151

Number 1 | Number 2 | Number 3

Number 1

Nuclear Fuel Management Optimization: A Work in Progress

Paul J. Turinsky

Nuclear Technology / Volume 151 / Number 1 / July 2005 / Pages 3-8

Technical Paper / Advances in Nuclear Fuel Management - Overview / dx.doi.org/10.13182/NT05-A3626

Adaptive Core Simulation Employing Discrete Inverse Theory - Part I: Theory

Hany S. Abdel-Khalik, Paul J. Turinsky

Nuclear Technology / Volume 151 / Number 1 / July 2005 / Pages 9-21

Technical Paper / Advances in Nuclear Fuel Management - Core Physics and Fuel Management Methods, Analytical Tools, and Benchmarks / dx.doi.org/10.13182/NT05-A3627

Adaptive Core Simulation Employing Discrete Inverse Theory - Part II: Numerical Experiments

Hany S. Abdel-Khalik, Paul J. Turinsky

Nuclear Technology / Volume 151 / Number 1 / July 2005 / Pages 22-34

Technical Paper / Advances in Nuclear Fuel Management - Core Physics and Fuel Management Methods, Analytical Tools, and Benchmarks / dx.doi.org/10.13182/NT05-A3628

NFCSim: A Dynamic Fuel Burnup and Fuel Cycle Simulation Tool

Erich A. Schneider, Charles G. Bathke, Michael R. James

Nuclear Technology / Volume 151 / Number 1 / July 2005 / Pages 35-50

Technical Paper / Advances in Nuclear Fuel Management - Core Physics and Fuel Management Methods, Analytical Tools, and Benchmarks / dx.doi.org/10.13182/NT05-4

Accurate Tools to Model Advanced SVEA Fuel Designs

Juan J. Casal, Jan Krouthén, Manuel Albendea

Nuclear Technology / Volume 151 / Number 1 / July 2005 / Pages 51-59

Technical Paper / Advances in Nuclear Fuel Management - Core Physics and Fuel Management Methods, Analytical Tools, and Benchmarks / dx.doi.org/10.13182/NT05-A3630

Uncertainty Estimates in Cold Critical Eigenvalue Predictions

Atul A. Karve, Brian R. Moore, Vernon W. Mills, Gary N. Marrotte

Nuclear Technology / Volume 151 / Number 1 / July 2005 / Pages 60-69

Technical Paper / Advances in Nuclear Fuel Management - Core Physics and Fuel Management Methods, Analytical Tools, and Benchmarks / dx.doi.org/10.13182/NT05-A3631

Nondestructive Experimental Determination of the Pin-Power Distribution in Nuclear Fuel Assemblies

Staffan Jacobsson Svärd, Ane Håkansson, Anders Bäcklin, Otasowie Osifo, Christopher Willman, Peter Jansson

Nuclear Technology / Volume 151 / Number 1 / July 2005 / Pages 70-76

Technical Paper / Advances in Nuclear Fuel Management - Core Physics and Fuel Management Methods, Analytical Tools, and Benchmarks / dx.doi.org/10.13182/NT05-A3632

Automated Core Design

Yoko Kobayashi, Eitaro Aiyoshi

Nuclear Technology / Volume 151 / Number 1 / July 2005 / Pages 77-85

Technical Paper / Advances in Nuclear Fuel Management - Light Water Reactor Reloading Optimization / dx.doi.org/10.13182/NT05-A3633

Optimizing the Placement of Burnable Poisons in PWRs

Serkan Yilmaz, Kostadin Ivanov, Samuel Levine, Moussa Mahgerefteh

Nuclear Technology / Volume 151 / Number 1 / July 2005 / Pages 86-95

Technical Paper / Advances in Nuclear Fuel Management - Light Water Reactor Reloading Optimization / dx.doi.org/10.13182/NT05-A3634

Reducing Duration of Refueling Outage by Optimizing Core Design and Shuffling Sequence

P. H. Wakker, F. C. M. Verhagen, J. T. Van Bloois, W. R. Sutton III

Nuclear Technology / Volume 151 / Number 1 / July 2005 / Pages 96-105

Technical Paper / Advances in Nuclear Fuel Management - Light Water Reactor Reloading Optimization / dx.doi.org/10.13182/NT05-A3635

Number 2

Optimum Discharge Burnup and Cycle Length for PWRs

Jeffrey R. Secker, Baard J. Johansen, David L. Stucker, Odelli Ozer, Kostadin Ivanov, Serkan Yilmaz, E. H. Young

Nuclear Technology / Volume 151 / Number 2 / August 2005 / Pages 109-119

Technical Paper / Advances in Nuclear Fuel Management - Increased Enrichment/High Burnup and Light Water Reactor Fuel Cycle Optimization / dx.doi.org/10.13182/NT05-A3636

Extended Power Uprates and 2-yr Cycles for BWRs - Where Do We Go from Here?

Craig Brown, Ken Hartley, Jim Hulsman

Nuclear Technology / Volume 151 / Number 2 / August 2005 / Pages 120-125

Technical Paper / Advances in Nuclear Fuel Management - Increased Enrichment/High Burnup and Light Water Reactor Fuel Cycle Optimization / dx.doi.org/10.13182/NT05-1

Effect of Highly Enriched/Highly Burnt UO2 Fuels on Fuel Cycle Costs, Radiotoxicity, and Nuclear Design Parameters

Robert Gregg, Andrew Worrall

Nuclear Technology / Volume 151 / Number 2 / August 2005 / Pages 126-132

Technical Paper / Advances in Nuclear Fuel Management - Increased Enrichment/High Burnup and Light Water Reactor Fuel Cycle Optimization / dx.doi.org/10.13182/NT05-A3638

Use of Sensitivity and Uncertainty Analysis in the Design of Reactor Physics and Criticality Benchmark Experiments for Advanced Nuclear Fuel

B. T. Rearden, W. J. Anderson, G. A. Harms

Nuclear Technology / Volume 151 / Number 2 / August 2005 / Pages 133-158

Technical Paper / Advances in Nuclear Fuel Management - Increased Enrichment/High Burnup and Light Water Reactor Fuel Cycle Optimization / dx.doi.org/10.13182/NT05-A3639

Plutonium Recycling in Light Water Reactors at Framatome ANP: Status and Trends

Dieter Porsch, Walter Stach, Pascal Charmensat, Michel Pasquet

Nuclear Technology / Volume 151 / Number 2 / August 2005 / Pages 159-167

Technical Paper / Advances in Nuclear Fuel Management - Use of Alternate Fuels in Light Water Reactors / dx.doi.org/10.13182/NT05-A3640

Use of Thorium in Light Water Reactors

Michael Todosow, A. Galperin, S. Herring, M. Kazimi, T. Downar, A. Morozov

Nuclear Technology / Volume 151 / Number 2 / August 2005 / Pages 168-176

Technical Paper / Advances in Nuclear Fuel Management - Use of Alternate Fuels in Light Water Reactors / dx.doi.org/10.13182/NT151-168

New Fuel Cycle and Fuel Management Options in Heavy Liquid Metal-Cooled Reactors

Ehud Greenspan, Pavel Hejzlar, Hiroshi Sekimoto, Georgy Toshinsky, David Wade

Nuclear Technology / Volume 151 / Number 2 / August 2005 / Pages 177-191

Technical Paper / Advances in Nuclear Fuel Management - Fuel Management of Reactors Other Than Light Water Reactors / dx.doi.org/10.13182/NT05-A3642

Feasibility of Burning First- and Second-Generation Plutonium in Pebble Bed High-Temperature Reactors

J. B. M. De Haas, J. C. Kuijper

Nuclear Technology / Volume 151 / Number 2 / August 2005 / Pages 192-200

Technical Paper / Advances in Nuclear Fuel Management - Fuel Management of Reactors Other Than Light Water Reactors / dx.doi.org/10.13182/NT05-A3643

Accuracy of Monte Carlo Criticality Calculations During BR2 Operation

Silva Kalcheva, Edgar Koonen, Bernard Ponsard

Nuclear Technology / Volume 151 / Number 2 / August 2005 / Pages 201-219

Technical Paper / Advances in Nuclear Fuel Management - Fuel Management of Reactors Other Than Light Water Reactors / dx.doi.org/10.13182/NT05-A3644

Number 3

Fuel Design and Core Layout for a Gas-Cooled Fast Reactor

W. F. G. van Rooijen, J. L. Kloosterman, T. H. J. J. van der Hagen, H. van Dam

Nuclear Technology / Volume 151 / Number 3 / September 2005 / Pages 221-238

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT05-A3645

A Fast-Spectrum Test Reactor Concept

Youssef A. Shatilla, Eric P. Loewen

Nuclear Technology / Volume 151 / Number 3 / September 2005 / Pages 239-249

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT05-A3646

Wavelet-Based Method for Instability Analysis in Boiling Water Reactors

Gilberto Espinosa-Paredes, Alfonso Prieto-Guerrero, Alejandro Núñez-Carrera, Rodolfo Amador-García

Nuclear Technology / Volume 151 / Number 3 / September 2005 / Pages 250-260

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT05-A3647

RELAP5 Prediction of Transient Tests in the RD-14 Test Facility

Sukho Lee, Manwoong Kim, Hho-Jung Kim, John C. Lee

Nuclear Technology / Volume 151 / Number 3 / September 2005 / Pages 261-271

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT05-A3648

RELAP5-3D Validation Study Using MB-2 Prototypical Steam Generator Steady-State Data

A. Sawyer, M. Williamson, K. Zhao, A. Ruggles

Nuclear Technology / Volume 151 / Number 3 / September 2005 / Pages 272-280

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT05-A3649

Online Sensor Calibration Monitoring Uncertainty Estimation

J. Wesley Hines, Brandon Rasmussen

Nuclear Technology / Volume 151 / Number 3 / September 2005 / Pages 281-288

Technical Paper / Nuclear Plant Operations and Control / dx.doi.org/10.13182/NT05-A3650

A Novel Methodology for Processing of Plutonium-Bearing Waste as Ammonium Plutonium(III)-Oxalate

Sanjay Krishnarao Sali, Donal Marshal Noronha, Hemakant Ramkrishna Mhatre, Murlidhar Anna Mahajan, Keshav Chander, Suresh Kumar Aggarwal, Venkatarama Venugopal

Nuclear Technology / Volume 151 / Number 3 / September 2005 / Pages 289-296

Technical Paper / Reprocessing / dx.doi.org/10.13182/NT05-A3651

Gamma-Ray Irradiation and Contact with High-Alkalinity Sludge: Stability Studies of Mercury Fulminate

F. F. Fondeur, W. R. Wilmarth, T. B. Peters, S. D. Fink

Nuclear Technology / Volume 151 / Number 3 / September 2005 / Pages 297-302

Technical Paper / Radioisotopes / dx.doi.org/10.13182/NT05-A3652

Performance of a Clad Tungsten Rod Spallation Neutron Source Target

Walter F. Sommer, Stuart A. Maloy, McIntyre R. Louthan, Gordon J. Willcutt, Phillip D. Ferguson, Michael R. James

Nuclear Technology / Volume 151 / Number 3 / September 2005 / Pages 303-313

Technical Paper / Accelerators / dx.doi.org/10.13182/NT05-A3653

Inherent Safety of Fuels for Accelerator-Driven Systems

M. Eriksson, J. Wallenius, M. Jolkkonen, J. E. Cahalan

Nuclear Technology / Volume 151 / Number 3 / September 2005 / Pages 314-333

Technical Paper / Accelerators / dx.doi.org/10.13182/NT05-A3654

Thorium-Fueled Underground Power Plant Based on Molten Salt Technology

Ralph W. Moir, Edward Teller

Nuclear Technology / Volume 151 / Number 3 / September 2005 / Pages 334-340

Technical Note / Fission Reactors / dx.doi.org/10.13182/NT05-A3655

Field Emission-Type Scanning Electron Microscope for Examination of Irradiated Fuels

Ryou Yasuda, Naoaki Mita, Yasuharu Nishino, Masahito Nakata, Yukio Nozawa, Katsuya Harada, Teruo Kushida, Hidetoshi Amano

Nuclear Technology / Volume 151 / Number 3 / September 2005 / Pages 341-345

Technical Note / Materials for Nuclear Systems / dx.doi.org/10.13182/NT05-A3656

 
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