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Aerospace Nuclear Science & Technology
Organized to promote the advancement of knowledge in the use of nuclear science and technologies in the aerospace application. Specialized nuclear-based technologies and applications are needed to advance the state-of-the-art in aerospace design, engineering and operations to explore planetary bodies in our solar system and beyond, plus enhance the safety of air travel, especially high speed air travel. Areas of interest will include but are not limited to the creation of nuclear-based power and propulsion systems, multifunctional materials to protect humans and electronic components from atmospheric, space, and nuclear power system radiation, human factor strategies for the safety and reliable operation of nuclear power and propulsion plants by non-specialized personnel and more.
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Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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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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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Inverse Predictive Modeling of a Spent-Fuel Dissolver Model
James J. Peltz, Dan G. Cacuci
Nuclear Science and Engineering | Volume 184 | Number 1 | September 2016 | Pages 1-15
Technical Paper | doi.org/10.13182/NSE16-50
The Second-Order Adjoint Sensitivity Analysis Methodology for Nonlinear Systems—I: Theory
Dan G. Cacuci
Nuclear Science and Engineering | Volume 184 | Number 1 | September 2016 | Pages 16-30
Technical Paper | doi.org/10.13182/NSE16-16
The Second-Order Adjoint Sensitivity Analysis Methodology for Nonlinear Systems—II: Illustrative Application to a Nonlinear Heat Conduction Problem
Nuclear Science and Engineering | Volume 184 | Number 1 | September 2016 | Pages 31-52
Technical Paper | doi.org/10.13182/NSE16-31
Continuous-Energy Sensitivity Coefficients in the MORET Code
Alexis Jinaphanh, Nicolas Leclaire, Bertrand Cochet
Nuclear Science and Engineering | Volume 184 | Number 1 | September 2016 | Pages 53-68
Technical Paper | doi.org/10.13182/NSE16-2
Testing the Sampling-Based NUSS-RF Tool for the Nuclear Data–Related Global Sensitivity Analysis with Monte Carlo Neutronics Calculations
Ting Zhu, Alexander Vasiliev, Hakim Ferroukhi, Dimitri Rochman, Andreas Pautz
Nuclear Science and Engineering | Volume 184 | Number 1 | September 2016 | Pages 69-83
Technical Paper | doi.org/10.13182/NSE14-142
A Phonon-Based Covariance Methodology for ENDF S(α, β) and Thermal Neutron Inelastic Scattering Cross Sections
Jesse C. Holmes, Ayman I. Hawari, Michael L. Zerkle
Nuclear Science and Engineering | Volume 184 | Number 1 | September 2016 | Pages 84-113
Technical Paper | doi.org/10.13182/NSE15-89
Angle-Dependent Double-Differential Neutron Emission Cross Sections of 3H(t,n) Between 5.98 and 19.14 MeV and Evidence of 4H as Intermediate Reaction Product
M. Drosg, M. M. Steurer, E. Jericha, D. M. Drake
Nuclear Science and Engineering | Volume 184 | Number 1 | September 2016 | Pages 114-124
Technical Note | doi.org/10.13182/NSE16-56
Passive Detection of Small Low-Emission Sources: Two-Dimensional Numerical Case Studies
A. Olson, A. Ciabatti, Y. Hristova, P. Kuchment, J. Ragusa, M. Allmaras
Nuclear Science and Engineering | Volume 184 | Number 1 | September 2016 | Pages 125-150
Technical Note | doi.org/10.13182/NSE15-66
Comparison of 1-D/1-D Fusion Method and 1-D/1-D Hybrid Method in Two-Dimensional Neutron Transport Problems: Convergence Analysis and Numerical Results
Seungsu Yuk, Nam Zin Cho
Nuclear Science and Engineering | Volume 184 | Number 2 | October 2016 | Pages 151-167
Technical Paper | doi.org/10.13182/NSE15-128
A CMFD Acceleration Method for SP3 Advanced Nodal Method
Akio Yamamoto, Tatsuya Sakamoto, Tomohiro Endo
Nuclear Science and Engineering | Volume 184 | Number 2 | October 2016 | Pages 168-173
Technical Paper | doi.org/10.13182/NSE16-53
Calculation of Higher-Order Fluxes in Symmetric Cores—I: Theory
Jean Tommasi, Maxence Maillot, Gérald Rimpault
Nuclear Science and Engineering | Volume 184 | Number 2 | October 2016 | Pages 174-189
Technical Paper | doi.org/10.13182/NSE16-4
Calculation of Higher-Order Fluxes in Symmetric Cores—II: Implementation
Maxence Maillot, Jean Tommasi, Gérald Rimpault
Nuclear Science and Engineering | Volume 184 | Number 2 | October 2016 | Pages 190-207
Technical Paper | doi.org/10.13182/NSE16-5
Analysis of Stabilization Techniques for CMFD Acceleration of Neutron Transport Problems
M. Jarrett, B. Kochunas, A. Zhu, T. Downar
Nuclear Science and Engineering | Volume 184 | Number 2 | October 2016 | Pages 208-227
Technical Paper | doi.org/10.13182/NSE16-51
A Coarse-Mesh Coupled Neutronics and Thermal Fluids Method for Prismatic Cores
Kevin John Connolly, Alexander J. Huning, Farzad Rahnema, Srinivas Garimella
Nuclear Science and Engineering | Volume 184 | Number 2 | October 2016 | Pages 228-243
Technical Paper | doi.org/10.13182/NSE15-105
Fourier Method for Calculating Fission Chain Neutron Multiplicity Distributions
David H. Chambers, Hema Chandrasekaran, Sean E. Walston
Nuclear Science and Engineering | Volume 184 | Number 2 | October 2016 | Pages 244-253
Technical Paper | doi.org/10.13182/NSE15-109
Activation Cross Section for Reactions Induced by d-T Neutrons on Natural Yttrium
Junhua Luo, Li Jiang
Nuclear Science and Engineering | Volume 184 | Number 2 | October 2016 | Pages 254-262
Technical Paper | doi.org/10.13182/NSE16-15
Experimental Investigation on Characteristics of Boiling Two-Phase-Flow Instability in a Parallel-Multichannel Natural-Circulation System
Sapna Singh, A. K. Nayak, J. Aparna
Nuclear Science and Engineering | Volume 184 | Number 2 | October 2016 | Pages 263-279
Technical Paper | doi.org/10.13182/NSE15-125
Determination of Two-Phase Turbulent-Mixing Rate in Simulated Subchannels of a Natural-Circulation Pressure Tube–Type BWR
M. P. Sharma, A. K. Nayak
Nuclear Science and Engineering | Volume 184 | Number 2 | October 2016 | Pages 280-291
Technical Paper | doi.org/10.13182/NSE15-112
Reactor Safety Gap Evaluation of Accident-Tolerant Components and Severe Accident Analysis
M. T. Farmer, R. Bunt, M. Corradini, P. Ellison, M. Francis, J. Gabor, R. Gauntt, C. Henry, R. Linthicum, W. Luangdilok, R. Lutz, C. Paik, M. Plys, C. Rabiti, J. Rempe, K. Robb, R. Wachowiak
Nuclear Science and Engineering | Volume 184 | Number 3 | November 2016 | Pages 293-304
Technical Paper | doi.org/10.13182/NSE16-13
A Regulator’s Perspective on the State of the Art in Nuclear Thermal Hydraulics
Stephen M. Bajorek
Nuclear Science and Engineering | Volume 184 | Number 3 | November 2016 | Pages 305-311
Technical Paper | doi.org/10.13182/NSE16-21
DNS–Assisted Modeling of Bubbly Flows in Vertical Channels
Gretar Tryggvason, Ming Ma, Jiacai Lu
Nuclear Science and Engineering | Volume 184 | Number 3 | November 2016 | Pages 312-320
Technical Paper | doi.org/10.13182/NSE16-10
Analytical Stability Analogue for a Single-Phase Natural-Circulation Loop
Yousef M. Farawila, Donald R. Todd, Maurice J. Ades, José N. Reyes Jr.
Nuclear Science and Engineering | Volume 184 | Number 3 | November 2016 | Pages 321-333
Technical Paper | doi.org/10.13182/NSE16-24
Symbolic Dynamics Applied to the Identification of Flow Patterns Inside Tube Banks
Alexandre Vagtinski de Paula, Luiz Augusto Magalhães Endres, Sergio Viçosa Möller
Nuclear Science and Engineering | Volume 184 | Number 3 | November 2016 | Pages 334-345
Technical Paper | doi.org/10.13182/NSE16-30
Use of White Noise in TRACE/PARCS Analysis of ATWS with Instability
Tarek Zaki, Peter Yarsky
Nuclear Science and Engineering | Volume 184 | Number 3 | November 2016 | Pages 346-352
Technical Paper | doi.org/10.13182/NSE16-14
Effect of Collision Force on Well-Posedness and Stability of the Two-Fluid Model for Vertical Bubbly Flows
Avinash Vaidheeswaran, William D. Fullmer, Martin Lopez de Bertodano
Nuclear Science and Engineering | Volume 184 | Number 3 | November 2016 | Pages 353-362
Technical Paper | doi.org/10.13182/NSE16-23
Spectral Analysis of Single- and Two-Phase Bubbly DNS in Different Geometries
C. S. Brown, I. A. Bolotnov
Nuclear Science and Engineering | Volume 184 | Number 3 | November 2016 | Pages 363-376
Technical Paper | doi.org/10.13182/NSE15-126
Phase-Field Modeling of Binary Eutectic Alloy Solidification with Convection
Stefan Meyer, Ivan Otic, Xu Cheng
Nuclear Science and Engineering | Volume 184 | Number 3 | November 2016 | Pages 377-387
Technical Paper | doi.org/10.13182/NSE16-6
Sampling Variance and Bias of the Wilks Conservative Estimate of Confidence Intervals
Jan Peter Hessling
Nuclear Science and Engineering | Volume 184 | Number 3 | November 2016 | Pages 388-399
Technical Paper | doi.org/10.13182/NSE16-8
Global Sensitivity Analysis of Transient Code Output Applied to a Reflood Experiment Model Using the TRACE Code
Damar Wicaksono, Omar Zerkak, Andreas Pautz
Nuclear Science and Engineering | Volume 184 | Number 3 | November 2016 | Pages 400-429
Technical Paper | doi.org/10.13182/NSE16-37
Methodology for Characterizing Representativeness Uncertainty in Orifice Plate Mass Flow Rate Measurements Using CFD Simulations
Uuganbayar Otgonbaatar, Emilio Baglietto, Neil Todreas
Nuclear Science and Engineering | Volume 184 | Number 3 | November 2016 | Pages 430-440
Technical Paper | doi.org/10.13182/NSE16-9
A Discussion of Uncertainty Quantification for CHF as Performed in COBRA-IE
David L. Aumiller, Michael J. Meholic
Nuclear Science and Engineering | Volume 184 | Number 3 | November 2016 | Pages 441-452
Technical Paper | doi.org/10.13182/NSE16-41
An Assessment of Void Fraction Data with COBRA-IE
Nuclear Science and Engineering | Volume 184 | Number 3 | November 2016 | Pages 453-462
Technical Paper | doi.org/10.13182/NSE16-42
Large Open Region Interfacial Drag Modeling Package in COBRA-IE
David L. Aumiller, Jeffrey W. Lane
Nuclear Science and Engineering | Volume 184 | Number 3 | November 2016 | Pages 463-471
Technical Paper | doi.org/10.13182/NSE16-12
A Collision Probability and MOC-Based Lattice and Burnup Code for Analysis of LWR Fuel Assemblies
Sherly Ray, S. B. Degweker, Rashmi Rai, K. P. Singh
Nuclear Science and Engineering | Volume 184 | Number 4 | December 2016 | Pages 473-494
Technical Paper | doi.org/10.13182/NSE15-127
Heterogeneous Pseudo-Resonant Isotope Method for Resolved Resonance Interference Treatment in Resonance Self-Shielding Calculation
Tiejun Zu, Qian Zhang, Hongchun Wu, Liangzhi Cao, Qingming He, Won Sik Yang
Nuclear Science and Engineering | Volume 184 | Number 4 | December 2016 | Pages 495-513
Technical Paper | doi.org/10.13182/NSE16-65
Nonlinear Diffusion Acceleration Method with Multigrid in Energy for k-Eigenvalue Neutron Transport Problems
Luke R. Cornejo, Dmitriy Y. Anistratov
Nuclear Science and Engineering | Volume 184 | Number 4 | December 2016 | Pages 514-526
Technical Paper | doi.org/10.13182/NSE16-78
Parallel Sn Sweep Scheduling Algorithm on Unstructured Grids for Multigroup Time-Dependent Particle Transport Equations
Jie Liu, Lihua Chi, Wang QingLin, Gong Chunye, Jiang Jie, Gan Xinbiao, Li Shengguo, Qingfeng Hu, Tom Masterson
Nuclear Science and Engineering | Volume 184 | Number 4 | December 2016 | Pages 527-536
Technical Paper | doi.org/10.13182/NSE15-53
Stochastic Theory of the Fission Chamber Current Generated by Non-Poissonian Neutrons
Lénard Pál, Imre Pázsit
Nuclear Science and Engineering | Volume 184 | Number 4 | December 2016 | Pages 537-550
Technical Paper | doi.org/10.13182/NSE16-18
Monte Carlo Approach of Effective Delayed Neutron Fraction by k-Ratio Method with External Neutron Source
Masao Yamanaka, Cheol Ho Pyeon, Tsuyoshi Misawa
Nuclear Science and Engineering | Volume 184 | Number 4 | December 2016 | Pages 551-560
Technical Paper | doi.org/10.13182/NSE15-107
Ranking the Importance of Nuclear Reactions for Activation and Transmutation Events
Wayne Arter, J. Guy Morgan, Samuel D. Relton, Nicholas J. Higham
Nuclear Science and Engineering | Volume 184 | Number 4 | December 2016 | Pages 561-574
Technical Paper | doi.org/10.13182/NSE15-23
Operational Experience Data Analysis on Events Related to Maintenance at Nuclear Power Plants
Antonio Ballesteros, Radian Sanda, Michael Maqua, Jean-Luc Stephan
Nuclear Science and Engineering | Volume 184 | Number 4 | December 2016 | Pages 575-583
Technical Paper | doi.org/10.13182/NSE16-80
Pulsed Neutron Source Measurements in the BRAHMMA Accelerator-Driven Subcritical System
Tushar Roy, Nirmal Ray, Shefali Bajpai, Tarun Patel, Mayank Shukla, Yogesh Kashyap, Amar Sinha, S. C. Gadkari
Nuclear Science and Engineering | Volume 184 | Number 4 | December 2016 | Pages 584-590
Technical Paper | doi.org/10.13182/NSE16-81
High-Order Linear Discontinuous and Diamond Differencing Schemes Along Cyclic Characteristics
Alain Hébert
Nuclear Science and Engineering | Volume 184 | Number 4 | December 2016 | Pages 591-603
Technical Note | doi.org/10.13182/NSE16-82
