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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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Nuclear Science and Engineering
December 2024
Nuclear Technology
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November 2024
Latest News
Terrestrial Energy looks at EnergySolutions-owned sites for IMSR plants
Advanced reactor developer Terrestrial Energy and Utah-based waste management company EnergySolutions announced they have signed a memorandum of understanding to collaborate on the siting and deployment of Terrestrial Energy’s integral molten salt reactor plants at EnergySolutions-owned sites.
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Approximate Solution and Application of the Survival Probability Diffusion Equation
Scott D. Ramsey, Gregory J. Hutchens
Nuclear Science and Engineering | Volume 170 | Number 1 | January 2012 | Pages 1-15
Technical Paper | doi.org/10.13182/NSE10-26
Proliferation-Resistant Fuel for CANDU Reactors
Yigal Ronen, M. Aboudy, D. Regev
Nuclear Science and Engineering | Volume 170 | Number 1 | January 2012 | Pages 16-26
Technical Paper | doi.org/10.13182/NSE10-51
Chaotic Data Encryption for Long-Distance Monitoring of Nuclear Reactors
Günyaz Ablay, Can Emre Koksal, Tunc Aldemir
Nuclear Science and Engineering | Volume 170 | Number 1 | January 2012 | Pages 27-43
Technical Paper | doi.org/10.13182/NSE10-21
Measurement of 232Th(n,)233Th, 98Mo(n,)99Mo, 186W(n,)187W, 115In(n,)116m1In, and 92Mo(n,p)92mNb Cross Sections in the Energy Range of 1.6 to 3.7 MeV
Megha Bhike, B. J. Roy, A. Saxena, R. K. Choudhury, S. Ganesan
Nuclear Science and Engineering | Volume 170 | Number 1 | January 2012 | Pages 44-53
Technical Paper | doi.org/10.13182/NSE10-63
Peelle's Pertinent Puzzle: A Fake Due to Improper Analysis
Denise Neudecker, Rudolf Frühwirth, Helmut Leeb
Nuclear Science and Engineering | Volume 170 | Number 1 | January 2012 | Pages 54-60
Technical Paper | doi.org/10.13182/NSE11-20
Studies on Production of Neutrons in the Spallation Reactions Using the Monte Carlo Code MCNPX
Heba Louis, Esmaat Amin, Moustafa Aziz, Ibrahim Bashter
Nuclear Science and Engineering | Volume 170 | Number 1 | January 2012 | Pages 61-65
Technical Paper | doi.org/10.13182/NSE11-11
Correcting the Cusping Problem in Three-Dimensional Transients Through NEM Modification
Zelmo Rodrigues de Lima, Aquilino Senra Martinez, Fernando Carvalho da Silva, Antonio Carlos Marques Alvim
Nuclear Science and Engineering | Volume 170 | Number 1 | January 2012 | Pages 66-74
Technical Note | doi.org/10.13182/NSE10-67TN
On the Method ASCM for the Solution of the External Source Problem in a Slightly Subcritical Reactor
Sherly Ray, R. S. Modak
Nuclear Science and Engineering | Volume 170 | Number 1 | January 2012 | Pages 75-86
Technical Note | doi.org/10.13182/NSE10-87TN
Cross-Section Uncertainty Propagation in the Multigroup Slowing-Down Equations Using Probability Table Formalism
Cheikh M. Diop, Mireille Coste-Delclaux, Sébastien Lahaye
Nuclear Science and Engineering | Volume 170 | Number 1 | January 2012 | Pages 87-97
Technical Note | doi.org/10.13182/NSE10-94TN
Highly Efficient, Exact Quadratures for Three-Dimensional Discrete Ordinates Transport Calculations
Cory D. Ahrens
Nuclear Science and Engineering | Volume 170 | Number 1 | January 2012 | Pages 98-101
Technical Note | doi.org/10.13182/NSE10-69TN
An Efficient Multiproblem Strategy for Accurate Solutions of Linear Particle Transport Problems in Spherical Geometry
Paolo Picca, Roberto Furfaro, Barry D. Ganapol
Nuclear Science and Engineering | Volume 170 | Number 2 | February 2012 | Pages 103-124
Technical Paper | doi.org/10.13182/NSE11-05
Parallel Fission Bank Algorithms in Monte Carlo Criticality Calculations
Paul K. Romano, Benoit Forget
Nuclear Science and Engineering | Volume 170 | Number 2 | February 2012 | Pages 125-135
Technical Paper | doi.org/10.13182/NSE10-98
A Probabilistic Physics-of-Failure Approach to Prediction of Steam Generator Tube Rupture Frequency
Kaushik Chatterjee, Mohammad Modarres
Nuclear Science and Engineering | Volume 170 | Number 2 | February 2012 | Pages 136-150
Technical Paper | doi.org/10.13182/NSE11-27
Analysis of the Core Power Response During a PWR Rod Ejection Transient Using the PARCS Nodal Code and the DeCART MOC Code
Mathieu Hursin, Thomas J. Downar, Brendan Kochunas
Nuclear Science and Engineering | Volume 170 | Number 2 | February 2012 | Pages 151-167
Technical Paper | doi.org/10.13182/NSE10-75
Gradient-Enhanced Universal Kriging for Uncertainty Propagation
Brian A. Lockwood, Mihai Anitescu
Nuclear Science and Engineering | Volume 170 | Number 2 | February 2012 | Pages 168-195
Technical Paper | doi.org/10.13182/NSE10-86
A Technique for Accounting for Multigroup Cross-Section Interdependence in Sensitivity Calculations
Kirill Fedorovich Raskach
Nuclear Science and Engineering | Volume 170 | Number 2 | February 2012 | Pages 196-206
Technical Paper | doi.org/10.13182/NSE11-09
Novel Investigation of Iron Cross Sections via Spherical Shell Transmission Measurements and Particle Transport Calculations for Material Embrittlement Studies
Michael T. Wenner, Alireza Haghighat, James M. Adams, Allan D. Carlson, Steven M. Grimes, Thomas N. Massey
Nuclear Science and Engineering | Volume 170 | Number 3 | March 2012 | Pages 207-233
Technical Paper | doi.org/10.13182/NSE09-30
Kernel Density Estimation Method for Monte Carlo Global Flux Tallies
Kaushik Banerjee, William R. Martin
Nuclear Science and Engineering | Volume 170 | Number 3 | March 2012 | Pages 234-250
Technical Paper | doi.org/10.13182/NSE10-77
An Innovative Method to Measure the Gamma-Ray Emission Probabilities in the Decay of 238Np and 233Pa
P. Leconte, J.-P. Hudelot, M. Antony, J. Di-Salvo, D. Bernard
Nuclear Science and Engineering | Volume 170 | Number 3 | March 2012 | Pages 251-264
Technical Paper | doi.org/10.13182/NSE11-14
Evaluation and Adjustment of the Neutron-Induced Reactions of 63,65Cu
D. Rochman, A. J. Koning
Nuclear Science and Engineering | Volume 170 | Number 3 | March 2012 | Pages 265-279
Technical Paper | doi.org/10.13182/NSE11-37
Computational Schemes for Online Flux Mapping System in a Large-Sized Pressurized Heavy Water Reactor
Surendra Mishra , R. S. Modak, S. Ganesan
Nuclear Science and Engineering | Volume 170 | Number 3 | March 2012 | Pages 280-289
Technical Paper | doi.org/10.13182/NSE10-84
Core Temperature Monitoring System for Prototype Fast Breeder Reactor
M. Sakthivel, K. Madhusoodanan
Nuclear Science and Engineering | Volume 170 | Number 3 | March 2012 | Pages 290-293
Technical Paper | doi.org/10.13182/NSE11-07
