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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.
Meeting Spotlight
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
Standards Program
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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Feb 2025
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Nuclear Science and Engineering
March 2025
Nuclear Technology
Fusion Science and Technology
February 2025
Latest News
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.
Jump to:
Nuclear Forensics Methodology for Reactor-Type Attribution of Chemically Separated Plutonium
Jeremy M. Osborn, Evans D. Kitcher, Jonathan D. Burns, Charles M. Folden, III, Sunil S. Chirayath
Nuclear Technology | Volume 201 | Number 1 | January 2018 | Pages 1-10
Technical Paper | doi.org/10.1080/00295450.2017.1401442
A Nuclear Jet at Chernobyl Around 21:23:45 UTC on April 25, 1986
Lars-Erik De Geer, Christer Persson, Henning Rodhe
Nuclear Technology | Volume 201 | Number 1 | January 2018 | Pages 11-22
Technical Paper | doi.org/10.1080/00295450.2017.1384269
Wear Depth Prediction for Steam Generator Tubes Using an Estimated In Situ Wear Coefficient
Chi-Yong Park, Huinam Rhee, Ki-Wahn Ryu
Nuclear Technology | Volume 201 | Number 1 | January 2018 | Pages 23-40
Technical Paper | doi.org/10.1080/00295450.2017.1392396
A Feasibility Study on the Transmutation of 100Mo to 99mTc with Laser-Compton Scattering Photons
Jiyoung Lee, Haseeb ur Rehman, Yonghee Kim
Nuclear Technology | Volume 201 | Number 1 | January 2018 | Pages 41-51
Technical Paper | doi.org/10.1080/00295450.2017.1392397
High-Temperature Oxidation of a Sponge-Based E110 Cladding Tube Material: Weight Gain and Reaction Layer Kinetics
J. Krejčí, V. Vrtílková, J. Kabátová, A. Přibyl, P. Gajdoš, D. Rada, J. Šustr
Nuclear Technology | Volume 201 | Number 1 | January 2018 | Pages 52-65
Technical Paper | doi.org/10.1080/00295450.2017.1389595
Numeric Determination and Validation of Neutron-Induced Radioactive Nuclide Inventories for Decommissioning and Dismantling of Light Water Reactors
Peter-W. Phlippen, Luc Schlömer, Michael Nekipelov, Roger Vallentin, Bernard Lukas, Stefan Palm, Thomas Mispagel
Nuclear Technology | Volume 201 | Number 1 | January 2018 | Pages 66-79
Technical Paper | doi.org/10.1080/00295450.2017.1399039
Novel Methodologies for Modeling the Net Fission-Poison Reactivity Transients to Accurately Predict Criticals and Hot-Startup ECPs for the MURR Core
N. J. Peters, K. Kutikkad
Nuclear Technology | Volume 201 | Number 1 | January 2018 | Pages 80-98
Technical Paper | doi.org/10.1080/00295450.2017.1398582
Hydraulic and Heated Equivalent Diameters Used in Heat Transfer Correlations
Juliana P. Duarte, Michael L. Corradini
Nuclear Technology | Volume 201 | Number 1 | January 2018 | Pages 99-102
Technical Note | doi.org/10.1080/00295450.2017.1389594
Natural Heat Convective Coefficient Measurements Around a Large-Diameter Cylindrical Surface Equipped with Axial Fins
Olivier Bardon, Ludovic Garnier
Nuclear Technology | Volume 201 | Number 2 | February 2018 | Pages 103-112
Technical Paper | doi.org/10.1080/00295450.2017.1409054
Radiation-Induced Damage–Based System and Method for Indirectly Monitoring High-Dose Ionizing Radiation
Karen Colins, Yu Liu, Liqian Li, Kiranpreet Birdee
Nuclear Technology | Volume 201 | Number 2 | February 2018 | Pages 113-121
Technical Paper | doi.org/10.1080/00295450.2017.1411718
Use of Er Burnable Absorber for Improvement of CANDU6 Safety Parameters
Mohammad Abdul Motalab, Woosong Kim, Yonghee Kim
Nuclear Technology | Volume 201 | Number 2 | February 2018 | Pages 122-137
Technical Paper | doi.org/10.1080/00295450.2017.1414541
Measurement and Analysis for Determination of PCR of the CANDU6 Core
Jaeha Kim, Mohammad Abdul Motalab, Yonghee Kim, Gwangsoo Kim
Nuclear Technology | Volume 201 | Number 2 | February 2018 | Pages 138-154
Technical Paper | doi.org/10.1080/00295450.2017.1415087
Development of Chinese Female Computational Phantom Rad-Human and Its Application in Radiation Dosimetry Assessment
Yican Wu, Mengyun Cheng, Wen Wang, Jing Song, Shengpeng Yu, Pengcheng Long, Liqin Hu
Nuclear Technology | Volume 201 | Number 2 | February 2018 | Pages 155-164
Technical Paper | doi.org/10.1080/00295450.2017.1411717
Enhancing Workload Assessments for Validation Activities Associated with DBA and BDBA Scenarios
Aaron Derouin, Alice Salway
Nuclear Technology | Volume 201 | Number 2 | February 2018 | Pages 165-173
Technical Paper | doi.org/10.1080/00295450.2017.1413922
Calibrations of the FDS Long Counter for Neutron Fluence Measurement
Bing Hong, Chao Liu, Taosheng Li, Yongfeng Wang, Yanan Li, Mohamed Mazunga
Nuclear Technology | Volume 201 | Number 2 | February 2018 | Pages 174-179
Technical Paper | doi.org/10.1080/00295450.2017.1406270
Safety Criteria and Dependability Management Practices: A Case Study with I&C Systems of Prototype Fast Breeder Reactor
Srikantam Sravanthi, R. Dheenadhayalan, K. Madhusoodanan, K. Devan
Nuclear Technology | Volume 201 | Number 2 | February 2018 | Pages 180-189
Technical Note | doi.org/10.1080/00295450.2017.1407594
ATR Compendium: Irradiation Test Capabilities
Samuel E. Bays, Gilles J. Youinou, Misti Lillo, Paul Gilbreath
Nuclear Technology | Volume 201 | Number 3 | March 2018 | Pages 191-208
Critical Review | doi.org/10.1080/00295450.2018.1432967
Upgrading Limiting Peak-Power Analysis Techniques with Modern Validation and Uncertainty Quantification for the Advanced Test Reactor
Samuel E. Bays, Cliff B. Davis, Periann A. Archibald
Nuclear Technology | Volume 201 | Number 3 | March 2018 | Pages 209-227
Technical Paper | doi.org/10.1080/00295450.2017.1415091
Extension of the Advanced Test Reactor Operating Envelope Via Enhanced Reactor Physics Validation Techniques
Joseph W. Nielsen, David W. Nigg, Daren R. Norman
Nuclear Technology | Volume 201 | Number 3 | March 2018 | Pages 228-246
Technical Paper | doi.org/10.1080/00295450.2017.1356647
Evaluation of the Enhanced LEU Fuel (ELF) Design for Conversion of the Advanced Test Reactor to a Low-Enrichment Fuel Cycle
Mark D. DeHart, Zain Karriem, Michael A. Pope
Nuclear Technology | Volume 201 | Number 3 | March 2018 | Pages 247-266
Technical Paper | doi.org/10.1080/00295450.2017.1322451
Evaluation of Corrosion in YA-Type ATR Fuel Element During Reactor PALM Cycle 153B
Jeffrey O. Brower, Michael V. Glazoff, Thomas J. Eiden, Aleksey V. Rezvoi
Nuclear Technology | Volume 201 | Number 3 | March 2018 | Pages 267-285
Technical Paper | doi.org/10.1080/00295450.2017.1341278
Reducing Uncertainty in Hydrodynamic Modeling of ATR Experiments Via Flow Testing, Validation, and Optimization
W. F. Jones, W. R. Marcum, A. W. Weiss, C. B. Jensen, G. L. Hawkes, P. E. Murray, D. S. Crawford, J. W. Herter, J. C. Kennedy, N. E. Woolstenhulme, J. D. Wiest, D. B. Chapman, T. K. Howard, G. D. Latimer, A. M. Phillips
Nuclear Technology | Volume 201 | Number 3 | March 2018 | Pages 286-303
Technical Paper | doi.org/10.1080/00295450.2017.1407907
