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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Nuclear Technology
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February 2025
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Colin Judge: Testing structural materials in Idaho’s newest hot cell facility
Idaho National Laboratory’s newest facility—the Sample Preparation Laboratory (SPL)—sits across the road from the Hot Fuel Examination Facility (HFEF), which started operating in 1975. SPL will host the first new hot cells at INL’s Materials and Fuels Complex (MFC) in 50 years, giving INL researchers and partners new flexibility to test the structural properties of irradiated materials fresh from the Advanced Test Reactor (ATR) or from a partner’s facility.
Materials meant to withstand extreme conditions in fission or fusion power plants must be tested under similar conditions and pushed past their breaking points so performance and limitations can be understood and improved. Once irradiated, materials samples can be cut down to size in SPL and packaged for testing in other facilities at INL or other national laboratories, commercial labs, or universities. But they can also be subjected to extreme thermal or corrosive conditions and mechanical testing right in SPL, explains Colin Judge, who, as INL’s division director for nuclear materials performance, oversees SPL and other facilities at the MFC.
SPL won’t go “hot” until January 2026, but Judge spoke with NN staff writer Susan Gallier about its capabilities as his team was moving instruments into the new facility.
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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 | 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 | doi.org/10.13182/NT05-A3627
Adaptive Core Simulation Employing Discrete Inverse Theory - Part II: Numerical Experiments
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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | doi.org/10.13182/NT05-A3635
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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | doi.org/10.13182/NT05-A3644
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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | doi.org/10.13182/NT05-A3656
