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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.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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Site acquired for GLE laser enrichment plant
Global Laser Enrichment (GLE) has acquired a 665-acre parcel of land for its planned Paducah Laser Enrichment Facility (PLEF) in Kentucky.
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Second-Order Adjoint Sensitivity and Uncertainty Analysis of a Heat Transport Benchmark Problem—I: Analytical Results
Dan G. Cacuci
Nuclear Science and Engineering | Volume 183 | Number 1 | May 2016 | Pages 1-21
Technical Paper | doi.org/10.13182/NSE15-81
Second-Order Adjoint Sensitivity and Uncertainty Analysis of a Heat Transport Benchmark Problem—II: Computational Results Using G4M Reactor Thermal-Hydraulic Parameters
Dan G. Cacuci, Milica Ilic, Madalina C. Badea, Ruixian Fang
Nuclear Science and Engineering | Volume 183 | Number 1 | May 2016 | Pages 22-38
Technical Paper | doi.org/10.13182/NSE15-80
Discontinuity Factors for Simplified P3 Theory
Akio Yamamoto, Tatsuya Sakamoto, Tomohiro Endo
Nuclear Science and Engineering | Volume 183 | Number 1 | May 2016 | Pages 39-51
Technical Paper | doi.org/10.13182/NSE15-102
First Flight Escape Probability and Uncollided Flux of Nuclear Particles in Convex Bodies with Spherical Symmetry
P. Chiovaro, P. A. Di Maio, S. Garitta, E. Vallone, G. Vella
Nuclear Science and Engineering | Volume 183 | Number 1 | May 2016 | Pages 52-64
Technical Paper | doi.org/10.13182/NSE15-68
Improving the Accuracy of the Chebyshev Rational Approximation Method Using Substeps
Aarno Isotalo, Maria Pusa
Nuclear Science and Engineering | Volume 183 | Number 1 | May 2016 | Pages 65-77
Technical Paper | doi.org/10.13182/NSE15-67
Emulation-Based Calibration for Parameters in Parameterized Phonon Spectrum of ZrHx in TRIGA Reactor Simulations
Weixiong Zheng, Ryan G. McClarren
Nuclear Science and Engineering | Volume 183 | Number 1 | May 2016 | Pages 78-95
Technical Paper | doi.org/10.13182/NSE15-48
Accuracy of Reactor Physics Parameters in Thorium-Loaded Accelerator-Driven System Experiments at Kyoto University Critical Assembly
Masao Yamanaka, Cheol Ho Pyeon, Takahiro Yagi, Tsuyoshi Misawa
Nuclear Science and Engineering | Volume 183 | Number 1 | May 2016 | Pages 96-106
Technical Paper | doi.org/10.13182/NSE15-51
Code Development and Target Station Design for Chinese Accelerator-Driven System Project
Han-Jie Cai, Fen Fu, Jian-Yang Li, Ya-Ling Zhang, Xun-Chao Zhang, Xue-Song Yan, Zhi-Lei Zhang, Jian-Ya Xv, Mei-Ling Qi, Lei Yang
Nuclear Science and Engineering | Volume 183 | Number 1 | May 2016 | Pages 107-115
Technical Paper | doi.org/10.13182/NSE15-59
Burst Wait-Times in the Caliban Reactor Using the Gamma Probability Distribution Function
M. M. R. Williams
Nuclear Science and Engineering | Volume 183 | Number 1 | May 2016 | Pages 116-125
Technical Paper | doi.org/10.13182/NSE15-62
Arbitrary Lagrangian Eulerian Formulation for Sloshing Tank Analysis in Nuclear Engineering
M. Souli, A. V. Kultsep, E. Al-Bahkali, C. C. Pain, M. Moatamedi
Nuclear Science and Engineering | Volume 183 | Number 1 | May 2016 | Pages 126-134
Technical Paper | doi.org/10.13182/NSE15-63
Photonuclear Benchmarks of C, Al, Cu, Ta, Pb, and U from the ENDF/B-VII Cross-Section Library ENDF7U Using MCNPX
Matthias Frankl, Rafael Macián-Juan
Nuclear Science and Engineering | Volume 183 | Number 1 | May 2016 | Pages 135-142
Technical Paper | doi.org/10.13182/NSE15-47
Measuring the Neutron Signature of the t→d+n Triton Breakup Reaction and the Angle-Dependent Differential Cross Section of 6Li(n,t)4He at 2.32 MeV
M. Drosg
Nuclear Science and Engineering | Volume 183 | Number 1 | May 2016 | Pages 143-148
Technical Note | doi.org/10.13182/NSE15-65
Analysis of Multiple TRIGA-Based Molybdenum Production Reactor Cores Using a New Low-Enriched Uranium Target as Fuel
Andrew J. Hummel, Todd S. Palmer
Nuclear Science and Engineering | Volume 183 | Number 1 | May 2016 | Pages 149-159
Technical Note | doi.org/10.13182/NSE15-37
A Method for the Adaptive Selection of Angular Flux Expansion Orders in the Coarse Mesh Radiation Transport (COMET) Method
Kyle Remley, Farzad Rahnema
Nuclear Science and Engineering | Volume 183 | Number 2 | June 2016 | Pages 161-172
Technical Paper | doi.org/10.13182/NSE15-97
Optimization Algorithms for Multigroup Energy Structures
M. J. Fleming, L. W. G. Morgan, E. Shwageraus
Nuclear Science and Engineering | Volume 183 | Number 2 | June 2016 | Pages 173-184
Technical Paper | doi.org/10.13182/NSE15-55
A New Nodal Expansion Method with High-Order Moments for the Reduction of Numerical Oscillation in Convection-Diffusion Problems
Xiafeng Zhou, Jiong Guo, Fu Li
Nuclear Science and Engineering | Volume 183 | Number 2 | June 2016 | Pages 185-195
Technical Paper | doi.org/10.13182/NSE15-95
Convergence Analysis for the Method of Characteristics in Unstructured Meshes
Richard Sanchez, Simone Santandrea
Nuclear Science and Engineering | Volume 183 | Number 2 | June 2016 | Pages 196-213
Technical Paper | doi.org/10.13182/NSE15-78
Stochastic Analog Neutron Transport with TRIPOLI-4 and FREYA: Bayesian Uncertainty Quantification for Neutron Multiplicity Counting
J. M. Verbeke, O. Petit
Nuclear Science and Engineering | Volume 183 | Number 2 | June 2016 | Pages 214-228
Technical Paper | doi.org/10.13182/NSE15-82
Nuclear Reactor Transient Analysis by Continuous-Energy Monte Carlo Calculation Based on Predictor-Corrector Quasi-Static Method
YuGwon Jo, Bumhee Cho, Nam Zin Cho
Nuclear Science and Engineering | Volume 183 | Number 2 | June 2016 | Pages 229-246
Technical Paper | doi.org/10.13182/NSE15-100
Assessment of the Online Core Power Measured by a Boron Chamber in a Pool-Type Research Reactor Using a Nonlinear Calibration Model
L. Pantera, Y. Garnier, F. Jeury
Nuclear Science and Engineering | Volume 183 | Number 2 | June 2016 | Pages 247-260
Technical Paper | doi.org/10.13182/NSE15-77
Sensitivity of Cross Sections to Isotopic Densities for Subgroup Resonance Self-Shielding Calculations
M. Dion, G. Marleau
Nuclear Science and Engineering | Volume 183 | Number 2 | June 2016 | Pages 261-274
Technical Paper | doi.org/10.13182/NSE15-60
Preequilibrium Models for 63Cu(n, xp) Reaction in Neutrons at 9, 11, 14.8, and 15 MeV Using the EMPIRE 3.2 Code
L. Yettou
Nuclear Science and Engineering | Volume 183 | Number 2 | June 2016 | Pages 275-285
Technical Paper | doi.org/10.13182/NSE15-73
Neutron Total Cross Sections and Resonance Parameters of Palladium
Taofeng Wang, Guinyun Kim, Young Do Oh, Moo-Hyun Cho, In Soo Ko, Won Namkung
Nuclear Science and Engineering | Volume 183 | Number 2 | June 2016 | Pages 286-297
Technical Paper | doi.org/10.13182/NSE15-64
Double-Differential Angle-Dependent Three-Body Neutron Production Cross Sections of the Reaction 2H(t,n)X+Y at Triton Energies Between 5.97 and 16.41 MeV
M. Drosg, G. Haouat, D. M. Drake
Nuclear Science and Engineering | Volume 183 | Number 2 | June 2016 | Pages 298-303
Technical Note | doi.org/10.13182/NSE15-118
Predictive Modeling Applied to a Spent Fuel Dissolver Model—I: Adjoint Sensitivity Analysis
James J. Peltz, Dan G. Cacuci
Nuclear Science and Engineering | Volume 183 | Number 3 | July 2016 | Pages 305-331
Technical Paper | doi.org/10.13182/NSE15-98
Predictive Modeling Applied to a Spent Fuel Dissolver Model—II: Uncertainty Quantification and Reduction
James J. Peltz, Dan G. Cacuci, Aurelian F. Badea, Madalina C. Badea
Nuclear Science and Engineering | Volume 183 | Number 3 | July 2016 | Pages 332-346
Technical Paper | doi.org/10.13182/NSE15-99
Resonance Parameter Adjustment Based on Integral Experiments
Vladimir Sobes, Luiz Leal, Goran Arbanas, Benoit Forget
Nuclear Science and Engineering | Volume 183 | Number 3 | July 2016 | Pages 347-355
Technical Paper | doi.org/10.13182/NSE15-50
A Preliminary Examination of the Application of Unscented Transformation Technique to Error Propagation in Nonlinear Cases of Nuclear Data Science
Harshavardhan Kadvekar, Sana Khan, Sangeetha Prasanna Ram, Jayalekshmi Nair, S. Ganesan
Nuclear Science and Engineering | Volume 183 | Number 3 | July 2016 | Pages 356-370
Technical Paper | doi.org/10.13182/NSE15-103
Total Uncertainty Analysis for PWR Assembly Based on the Statistical Sampling Method
Tiejun Zu, Chenghui Wan, Liangzhi Cao, Hongchun Wu, Wei Shen
Nuclear Science and Engineering | Volume 183 | Number 3 | July 2016 | Pages 371-386
Technical Paper | doi.org/10.13182/NSE15-96
Improvement of Code Behavior in a Design of Experiments by Metamodeling
François Bachoc, Karim Ammar, Jean-Marc Martinez
Nuclear Science and Engineering | Volume 183 | Number 3 | July 2016 | Pages 387-406
Technical Paper | doi.org/10.13182/NSE15-108
Semianalytical Approximation and Lookup Table of Neutron Escape Probability from Rectangular Cell for Collision Probability Method
T. Matsumura
Nuclear Science and Engineering | Volume 183 | Number 3 | July 2016 | Pages 407-420
Technical Paper | doi.org/10.13182/NSE15-86
Calculating Time-Integral Quantities in Depletion Calculations
Aarno Isotalo
Nuclear Science and Engineering | Volume 183 | Number 3 | July 2016 | Pages 421-429
Technical Paper | doi.org/10.13182/NSE15-119
