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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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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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Optimizing Maintenance Strategies in Power Generation: Embracing Predictive and Preventive Approaches
In the high-stakes world of power generation, ensuring continuous operation and reducing downtime are central priorities. With the increasing complexity of power generation systems, maintenance practices are evolving to meet these demands more efficiently. Understanding the roles of Predictive Maintenance (PdM), Preventive Maintenance (PM), and Reactive Maintenance (Run-to-Failure) is crucial for maintenance professionals in the energy sector to make informed decisions about equipment management and long-term operational strategy.
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New Approach to Space-Dependent Kinetic Analysis by the Integral Kinetic Model
Hiroki Takezawa, Toru Obara
Nuclear Science and Engineering | Volume 171 | Number 1 | May 2012 | Pages 1-12
Technical Paper | doi.org/10.13182/NSE09-59
Neutron Balance Analysis for Sustainability of Breed-and-Burn Reactors
Florent Heidet, Ehud Greenspan
Nuclear Science and Engineering | Volume 171 | Number 1 | May 2012 | Pages 13-31
Technical Paper | doi.org/10.13182/NSE10-114
Development of a HEX-Z Partially Homogenized Benchmark Model for the FFTF Isothermal Physics Measurements
John D. Bess
Nuclear Science and Engineering | Volume 171 | Number 1 | May 2012 | Pages 32-40
Technical Paper | doi.org/10.13182/NSE10-100
Heuristic Methods for Assigning Spent Nuclear Fuel Assemblies to Canisters for Final Disposal
Timo Ranta, Frank Cameron
Nuclear Science and Engineering | Volume 171 | Number 1 | May 2012 | Pages 41-51
Technical Paper | doi.org/10.13182/NSE10-111
A Burnup-Dependent Isomeric Production Branching Ratio Treatment
W. Haeck, B. Cochet, L. Aguiar
Nuclear Science and Engineering | Volume 171 | Number 1 | May 2012 | Pages 52-68
Technical Paper | doi.org/10.13182/NSE10-99
Reliability Models of Aging Passive Components Informed by Materials Degradation Metrics to Support Long-Term Reactor Operations
Stephen D. Unwin, Peter P. Lowry, Michael Y. Toyooka
Nuclear Science and Engineering | Volume 171 | Number 1 | May 2012 | Pages 69-77
Technical Paper | doi.org/10.13182/NSE11-18
Measurement of Neutron-Induced Reaction Cross Sections in Zirconium Isotopes at Thermal, 2.45 MeV and 9.85 MeV Energies
P. M. Prajapati, S. Mukherjee, H. Naik, A. Goswami, S. V. Suryanarayana, S. C. Sharma, B. S. Shivashankar, V. K. Mulik, K. C. Jagdeesan, S. V. Thakre, S. Bisnoi, T. Patel, K. K. Rasheed, S. Ganesan
Nuclear Science and Engineering | Volume 171 | Number 1 | May 2012 | Pages 78-84
Technical Paper | doi.org/10.13182/NSE11-02
Evaluations of Fission Chain Yields for 239Pu from Fission-Spectrum Neutrons
I. J. Thompson, Y. M. X. M. Dardenne, J. M. Kenneally, A. Robertson, L. E. Ahle, C. A. Hagmann, R. A. Henderson, D. Vogt, C.-Y. Wu, W. Younes
Nuclear Science and Engineering | Volume 171 | Number 2 | June 2012 | Pages 85-135
Technical Paper | doi.org/10.13182/NSE10-101
Use of Zirconium-Based Moderators to Enhance Feedback Coefficients in a MOX-Fueled Sodium-Cooled Fast Reactor
Bruno Merk, Sören Kliem, Emil Fridman, Frank-Peter Weiss
Nuclear Science and Engineering | Volume 171 | Number 2 | June 2012 | Pages 136-149
Technical Paper | doi.org/10.13182/NSE10-58
A Comparison of Pulsing Characteristics of the Oregon State University TRIGA Reactor with FLIP and LEU Fuel
W. R. Marcum, T. S. Palmer, B. G. Woods, S. T. Keller, S. R. Reese, M. R. Hartman
Nuclear Science and Engineering | Volume 171 | Number 2 | June 2012 | Pages 150-164
Technical Paper | doi.org/10.13182/NSE11-25
Explicit Treatment of Thermal Motion in Continuous-Energy Monte Carlo Tracking Routines
Tuomas Viitanen, Jaakko Leppänen
Nuclear Science and Engineering | Volume 171 | Number 2 | June 2012 | Pages 165-173
Technical Paper | doi.org/10.13182/NSE11-36
Development of Self-Interrogation Neutron Resonance Densitometry to Quantify the Fissile Content in PWR Spent LEU and MOX Assemblies
Adrienne M. LaFleur, William S. Charlton, Howard O. Menlove, Martyn T. Swinhoe
Nuclear Science and Engineering | Volume 171 | Number 3 | July 2012 | Pages 175-191
Technical Paper | doi.org/10.13182/NSE11-40
Evaluation of 54Fe(n, 2n) Cross Sections and Their Covariance Data Below 20 MeV
Jing Qian, Min Jia, Tingjin Liu
Nuclear Science and Engineering | Volume 171 | Number 3 | July 2012 | Pages 192-203
Technical Paper | doi.org/10.13182/NSE10-93
Cross-Section Measurement of Thermal Neutron-Induced Fission on 243Cm
L. Popescu, J. Heyse, J. Wagemans, C. Wagemans
Nuclear Science and Engineering | Volume 171 | Number 3 | July 2012 | Pages 204-209
Technical Paper | doi.org/10.13182/NSE11-65
Refining the Accuracy of Predicting Physics Parameters at Research Reactors due to the Limitations in the Energy Balance Method Using MCNP and the ENDF Evaluations
N. J. Peters, J. C. McKibben, K. Kutikkad, W. H. Miller
Nuclear Science and Engineering | Volume 171 | Number 3 | July 2012 | Pages 210-219
Technical Paper | doi.org/10.13182/NSE10-71
An Orthonormally Weighted Standardized Time Series for the Error Estimation of Local Tallies in Monte Carlo Criticality Calculation
Taro Ueki
Nuclear Science and Engineering | Volume 171 | Number 3 | July 2012 | Pages 220-230
Technical Paper | doi.org/10.13182/NSE11-35
Evaluation and Uncertainty Analysis of the KRITZ-2 Critical Benchmark Experiments
Ivan Kodeli, Luka Snoj
Nuclear Science and Engineering | Volume 171 | Number 3 | July 2012 | Pages 231-238
Technical Paper | doi.org/10.13182/NSE11-62
On-the-Fly Doppler Broadening for Monte Carlo Codes
Gokhan Yesilyurt, William R. Martin, Forrest B. Brown
Nuclear Science and Engineering | Volume 171 | Number 3 | July 2012 | Pages 239-257
Technical Paper | doi.org/10.13182/NSE11-67
Time-Fractional Telegrapher's Equation (P1) Approximation for the Transport Equation
Gilberto Espinosa-Paredes, Marco Antonio Polo-Labarrios
Nuclear Science and Engineering | Volume 171 | Number 3 | July 2012 | Pages 258-264
Technical Note | doi.org/10.13182/NSE11-58
