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April 3–5, 2025
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Nuclear Science and Engineering
March 2025
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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Homogenization of Cross Sections and Computation of Discontinuity Factors for a Real 3-D BWR Bottom Reflector for Comparison with Lattice and Nodal Codes
John Loberg, Michael ÖSterlund, Klaes-Håkan Bejmer, Jan Blomgren, Jesper Kierkegaard
Nuclear Technology | Volume 177 | Number 1 | January 2012 | Pages 1-7
Technical Paper | Fission Reactors | doi.org/10.13182/NT12-A13323
Boiling Water Reactor Stability Analysis by TRACE/PARCS: Modeling Effects and Case Study of Time Versus Frequency Domain Approach
Rui Hu, Mujid S. Kazimi
Nuclear Technology | Volume 177 | Number 1 | January 2012 | Pages 8-28
Technical Paper | Fission Reactors | doi.org/10.13182/NT12-A13324
Evaluation of Plutonium Hemisphere Critical Experiments Partially Reflected by Steel and Oil
John D. Bess
Nuclear Technology | Volume 177 | Number 1 | January 2012 | Pages 29-35
Technical Paper | Reactor Safety | doi.org/10.13182/NT12-A13325
Modeling and Interpretation of Iodine Behavior in PHEBUS FPT-1 Containment with ASTEC and COCOSYS Codes
L. Bosland, G. Weber, W. Klein-Hessling, N. Girault, B. Clement
Nuclear Technology | Volume 177 | Number 1 | January 2012 | Pages 36-62
Technical Paper | Reactor Safety | doi.org/10.13182/NT12-A13326
Development of Erbia-Credit Super High Burnup Fuel: Experiments and Numerical Analyses
Masatoshi Yamasaki, Hironobu Unesaki, Akio Yamamoto, Toshikazu Takeda, Masaaki Mori
Nuclear Technology | Volume 177 | Number 1 | January 2012 | Pages 63-72
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT12-A13327
Analysis of MERCI Decay Heat Measurement for PWR UO2 Fuel Rod
J. C. Jaboulay, S. Bourganel
Nuclear Technology | Volume 177 | Number 1 | January 2012 | Pages 73-82
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT12-A13328
Minor Actinide Transmutation in GFR600
Zoltán Perkó, Jan Leen Kloosterman, Sándor Fehér
Nuclear Technology | Volume 177 | Number 1 | January 2012 | Pages 83-97
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT12-A13329
Numerical Study on the Turbulent Mixing Coefficient for Supercritical Fluids in Subchannels
Yina Zhang, Chao Zhang, Jin Jiang
Nuclear Technology | Volume 177 | Number 1 | January 2012 | Pages 98-106
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT12-A13330
Experimental Study of Two-Phase Flow Regime and Pressure Drop in a Particulate Bed Packed with Multidiameter Particles
Liangxing Li, Shengjie Gong, Weimin Ma
Nuclear Technology | Volume 177 | Number 1 | January 2012 | Pages 107-118
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT12-A13331
PARET-ANL Modeling of a SPERT-IV Experiment Under Different Departure from Nucleate Boiling Correlations
S. Chatzidakis, A. Ikonomopoulos, S. E. Day
Nuclear Technology | Volume 177 | Number 1 | January 2012 | Pages 119-131
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT12-A13332
Probabilistic Kernel Approach to Online Monitoring of Nuclear Power Plants
Miltiadis Alamaniotis, Andreas Ikonomopoulos, Lefteri H. Tsoukalas
Nuclear Technology | Volume 177 | Number 1 | January 2012 | Pages 132-145
Technical Paper | Nuclear Plant Operations and Control | doi.org/10.13182/NT12-A13333
New Strategy on the Evaluation of Dancoff Factor in a Pebble Bed Reactor Using Monte Carlo Method
Song Hyun Kim, Hong-Chul Kim, Jong Kyung Kim, Jea Man Noh
Nuclear Technology | Volume 177 | Number 2 | February 2012 | Pages 147-156
Technical Paper | Fission Reactors | doi.org/10.13182/NT12-A13362
Combined Micro and Macro Parameter Perturbation Theory and Application for BWR Lattice Design and Optimization
Albert G. Gu
Nuclear Technology | Volume 177 | Number 2 | February 2012 | Pages 157-175
Technical Paper | Fission Reactors | doi.org/10.13182/NT12-A13363
Three-Field Countercurrent Flow Limitation Model
Jeffrey W. Lane, David L. Aumiller, Jr., Lawrence E. Hochreiter, Fan-Bill Cheung
Nuclear Technology | Volume 177 | Number 2 | February 2012 | Pages 176-187
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT12-A13364
Experiments on Steam Condensation and Temperature Distribution Within the IRWST of APR-1400
S. N. Kim
Nuclear Technology | Volume 177 | Number 2 | February 2012 | Pages 188-202
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT12-A13365
A Study on the Steady-State and Transient Behavior of Natural Circulation in REX-10
Byeong-Il Jang, Moo Hwan Kim, Gyoodong Jeun
Nuclear Technology | Volume 177 | Number 2 | February 2012 | Pages 203-216
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT12-A13366
Experimental Study of the Effect of Graphite Dispersion on the Heat Transfer Phenomena in a Reactor Cavity Cooling System
Rodolfo Vaghetto, Luigi Capone, Yassin A. Hassan
Nuclear Technology | Volume 177 | Number 2 | February 2012 | Pages 217-230
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT12-A13367
Verification of a Simple Procedure to Simulate Solvent Extraction by Pulsed Columns
Tsuguyuki Kobayashi
Nuclear Technology | Volume 177 | Number 2 | February 2012 | Pages 231-244
Technical Paper | Reprocessing | doi.org/10.13182/NT12-A13368
Effects of Variable Saturation on the Thermal Analysis of the Engineered Barrier System for a Nuclear Waste Repository
Won-Jin Cho, Sangki Kwon
Nuclear Technology | Volume 177 | Number 2 | February 2012 | Pages 245-256
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT12-A13369
Thermal Creep Model for CWSR Zircaloy-4 Cladding Taking into Account the Annealing of the Irradiation Hardening
Chantal Cappelaere, Roger Limon, Christelle Duguay, Gérard Pinte, Michel Le Breton, Pol Bouffioux, Valérie Chabretou, Alain Miquet
Nuclear Technology | Volume 177 | Number 2 | February 2012 | Pages 257-272
Technical Paper | Materials for Nuclear Systems | doi.org/10.13182/NT12-A13370
Wavelet Approach for Operational Gamma Spectral Peak Detection: Preliminary Assessment
D. Yuan, P. Guss, T. Ashenfelter
Nuclear Technology | Volume 177 | Number 2 | February 2012 | Pages 273-284
Technical Paper | Radiation Measurements and General Instrumentation | doi.org/10.13182/NT12-A13371
Feasibility Studies for Speckle Interferometry Used to Measure Deformation in Nuclear Fuel Cladding
Alexandre Vauselle, Yves Pontillon, Laurent Gallais
Nuclear Technology | Volume 177 | Number 2 | February 2012 | Pages 285-292
Technical Paper | Radiation Measurements and General Instrumentation | doi.org/10.13182/NT12-A13372
Comparison of Sodium-Cooled Reactor Fuel-Handling Systems With and Without an Ex-Vessel Storage Tank
Yoshitaka Chikazawa, Masayuki Uzawa, Shinichi Usui, Katsuhiro Tozawa, Shoji Kotake
Nuclear Technology | Volume 177 | Number 3 | March 2012 | Pages 293-302
Technical Paper | Fission Reactors | doi.org/10.13182/NT12-A13476
ELECTRA: European Lead-Cooled Training Reactor
Janne Wallenius, Erdenechimeg Suvdantsetseg, Andrei Fokau
Nuclear Technology | Volume 177 | Number 3 | March 2012 | Pages 303-313
Technical Paper | Fission Reactors | doi.org/10.13182/NT12-A13477
Mathematical Modeling and Its Applications for Mass Flow in a Nuclear Fuel Cycle
Raphael Craplet, Joonhong Ahn
Nuclear Technology | Volume 177 | Number 3 | March 2012 | Pages 314-335
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT12-A13478
Experimental Study of Thermal Mixing in Flow Mixing Header Assembly of SMART
Jong-Won Kim, Jong-Soo Choi, Young-In Kim, Young-Jong Chung, Goon-Cherl Park
Nuclear Technology | Volume 177 | Number 3 | March 2012 | Pages 336-351
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT12-A13479
A Practical Method for Whole-Core Thermal Analysis of a Prismatic Gas-Cooled Reactor
Nam-Il Tak, Min-Hwan Kim, Hong Sik Lim, Jae Man Noh
Nuclear Technology | Volume 177 | Number 3 | March 2012 | Pages 352-365
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT12-A13480
A Functionally Graded Composite for Service in High-Temperature Lead- and Lead-Bismuth-Cooled Nuclear Reactors - I: Design
Michael Philip Short, Ronald George Ballinger
Nuclear Technology | Volume 177 | Number 3 | March 2012 | Pages 366-381
Technical Paper | Nuclear Plant Operations and Control | doi.org/10.13182/NT12-A13481
Integral Effect Tests on Transient Thermal-Hydraulic Behavior During a Steam Generator Tube Rupture Accident in the APR1400
Kyoung-Ho Kang, Hyun-Sik Park, Seok Cho, Nam-Hyun Choi, In-Cheol Chu, Byong-Jo Yun, Kyung-Doo Kim, Yeon-Sik Kim, Won-Pil Baek, Ki-Yong Choi
Nuclear Technology | Volume 177 | Number 3 | March 2012 | Pages 382-394
Technical Paper | Nuclear Plant Operations and Control | doi.org/10.13182/NT12-A13482
Nuclear Transmutations in HFIR's Beryllium Reflector and Their Impact on Reactor Operation and Reflector Disposal
David Chandler, G. Ivan Maldonado, L. D. Proctor, R. T. Primm, III
Nuclear Technology | Volume 177 | Number 3 | March 2012 | Pages 395-412
Technical Paper | Radioisotopes | doi.org/10.13182/NT12-A13483
Measurement and Modeling of Light Yield Nonproportionality in Neutron Detectors
Martin R. Williamson, Laurence F. Miller, Indraneel Sen
Nuclear Technology | Volume 177 | Number 3 | March 2012 | Pages 413-420
Technical Paper | Radiation Measurements and General Information | doi.org/10.13182/NT12-A13484