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Education, Training & Workforce Development
The Education, Training & Workforce Development Division provides communication among the academic, industrial, and governmental communities through the exchange of views and information on matters related to education, training and workforce development in nuclear and radiological science, engineering, and technology. Industry leaders, education and training professionals, and interested students work together through Society-sponsored meetings and publications, to enrich their professional development, to educate the general public, and to advance nuclear and radiological science and engineering.
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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ANS standard updated for determining meteorological information at nuclear facilities
Following approval in October from the American National Standards Institute, ANSI/ANS-3.11-2024, Determining Meteorological Information at Nuclear Facilities, was published in late November. This standard provides criteria for gathering, assembling, processing, storing, and disseminating meteorological information at commercial nuclear power plants, U.S. Department of Energy/National Nuclear Security Administration nuclear facilities, and other national or international nuclear facilities.
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Fuel Cycle Options for the Production and Utilization of Denatured Plutonium
C. H. M. Broeders, G. Kessler
Nuclear Science and Engineering | Volume 156 | Number 1 | May 2007 | Pages 1-23
Technical Paper | doi.org/10.13182/NSE07-A2681
Numerical Modeling of Evaporating Thin Liquid Film Instability on a Heated Cylindrical Rod with Parallel and Cross Vapor Flow
Seungwon Shin, S. I. Abdel-Khalik
Nuclear Science and Engineering | Volume 156 | Number 1 | May 2007 | Pages 24-39
Technical Paper | doi.org/10.13182/NSE07-A2682
Two-Dimensional Modeling of the Direct ECC Bypass in the APR1400 Downcomer
H. K. Cho, B. J. Yun, C.-H. Song, G. C. Park
Nuclear Science and Engineering | Volume 156 | Number 1 | May 2007 | Pages 40-54
Technical Paper | doi.org/10.13182/NSE07-A2683
Strategies in Stochastic Transport
A. Ziya Akcasu, Noel Corngold
Nuclear Science and Engineering | Volume 156 | Number 1 | May 2007 | Pages 55-67
Technical Paper | doi.org/10.13182/NSE07-A2684
The Description of Particle Transport Problems with Helical Symmetry
Edward W. Larsen
Nuclear Science and Engineering | Volume 156 | Number 1 | May 2007 | Pages 68-73
Technical Paper | doi.org/10.13182/NSE07-A2685
Fourier Convergence Analysis of Two-Dimensional/One-Dimensional Coupling Methods for the Three-Dimensional Neutron Diffusion Eigenvalue Problems
Hyun Chul Lee, Jae Man Noh, Hyung Kook Joo, Deokjung Lee, Thomas J. Downar
Nuclear Science and Engineering | Volume 156 | Number 1 | May 2007 | Pages 74-85
Technical Paper | doi.org/10.13182/NSE06-32
Investigations of 238U Captures to Total Fissions in a Westinghouse SVEA-96+ Assembly
U. C. Bergmann, P. Grimm, F. Jatuff, M. F. Murphy, R. Chawla
Nuclear Science and Engineering | Volume 156 | Number 1 | May 2007 | Pages 86-95
Technical Paper | doi.org/10.13182/NSE07-A2687
Process Development for Bulk Separation of Trivalent Actinides and Lanthanides from Radioactive High-Level Liquid Waste
Smitha Manohar, J. N. Sharma, B. V. Shah, P. K. Wattal
Nuclear Science and Engineering | Volume 156 | Number 1 | May 2007 | Pages 96-102
Technical Paper | doi.org/10.13182/NSE07-A2688
The 10B(n,0)/10B(n,1) Branching Ratio
F.-J. Hambsch, I. Ruskov
Nuclear Science and Engineering | Volume 156 | Number 1 | May 2007 | Pages 103-114
Technical Paper | doi.org/10.13182/NSE07-A2689
Differential Cross-Section Measurement for the 64Zn(n, )61Ni Reaction at 5.03 and 5.95 MeV
Guohui Zhang, Rongtai Cao, Jinxiang Chen, Guoyou Tang, Yu. M. Gledenov, M. Sedysheva, G. Khuukhenkhuu
Nuclear Science and Engineering | Volume 156 | Number 1 | May 2007 | Pages 115-119
Technical Paper | doi.org/10.13182/NSE07-A2690
An Improved Algebraic Collapsing Acceleration with General Boundary Conditions for the Characteristics Method
R. Le Tellier, A. Hébert
Nuclear Science and Engineering | Volume 156 | Number 2 | June 2007 | Pages 121-138
Technical Paper | doi.org/10.13182/NSE07-A2691
Error Comparison of Diamond Difference, Nodal, and Characteristic Methods for Solving Multidimensional Transport Problems with the Discrete Ordinates Approximation
J. I. Duo, Y. Y. Azmy
Nuclear Science and Engineering | Volume 156 | Number 2 | June 2007 | Pages 139-153
Technical Paper | doi.org/10.13182/NSE05-91
A Discretization Scheme for the Three-Dimensional Angular Fokker-Planck Operator
Jim E. Morel, Anil Prinja, John M. McGhee, Todd A. Wareing, Brian C. Franke
Nuclear Science and Engineering | Volume 156 | Number 2 | June 2007 | Pages 154-163
Technical Paper | doi.org/10.13182/NSE07-A2693
Nonanalog Implementations of Monte Carlo Isotopic Inventory Analysis
Phiphat Phruksarojanakun, Paul P. H. Wilson
Nuclear Science and Engineering | Volume 156 | Number 2 | June 2007 | Pages 164-179
Technical Paper | doi.org/10.13182/NSE07-A2694
An Optimum Approach to Monte Carlo Burnup
W. Haeck, B. Verboomen
Nuclear Science and Engineering | Volume 156 | Number 2 | June 2007 | Pages 180-196
Technical Paper | doi.org/10.13182/NSE07-A2695
Cross Sections for Neutron-Induced Fission of 235U, 238U, 209Bi, and natPb in the Energy Range from 33 to 200 MeV Measured Relative to n-p Scattering
R. Nolte, M. S. Allie, F. D. Brooks, A. Buffler, V. Dangendorf, J. P. Meulders, H. Schuhmacher, F. D. Smit, M. Weierganz
Nuclear Science and Engineering | Volume 156 | Number 2 | June 2007 | Pages 197-210
Technical Paper | doi.org/10.13182/NSE06-14
High Resolution Measurement of the 234U(n,f) Cross Section in the Neutron Energy Range from 0.5 eV to 100 keV
J. Heyse, C. Wagemans, L. De Smet, O. Serot, J. Wagemans, J. Van Gils
Nuclear Science and Engineering | Volume 156 | Number 2 | June 2007 | Pages 211-218
Technical Paper | doi.org/10.13182/NSE07-A2697
Isotope Separation Using Condensation Repression of the Laser Excited Gaseous CHCl3 Molecules Colliding with a Cold Wall
Jaewoo Kim, Jeff W. Eerkens, William H. Miller
Nuclear Science and Engineering | Volume 156 | Number 2 | June 2007 | Pages 219-228
Technical Paper | doi.org/10.13182/NSE07-A2698
Variation of Mass Attenuation Coefficient, Effective Atomic Number, and Electron Density with Incident Photon Energy of Some Organic Acids
Tejbir Singh, Paramjeet Kaur, Parjit S. Singh
Nuclear Science and Engineering | Volume 156 | Number 2 | June 2007 | Pages 229-243
Technical Paper | doi.org/10.13182/NSE07-A2699
Incineration of Light Water Reactor Waste in High-Temperature Gas Reactors: Axial Fuel Management and Efficiency of Americium and Curium Transmutation
Alberto Talamo, Waclaw Gudowski
Nuclear Science and Engineering | Volume 156 | Number 2 | June 2007 | Pages 244-266
Technical Note | doi.org/10.13182/NSE07-A2700
Isotopic and Energy Groupwise Dependence of Fuel Temperature Coefficient of Reactivity in Natural Uranium-Fueled Pressurized Heavy Water Reactors
Kannan Umasankari, S. Ganesan
Nuclear Science and Engineering | Volume 156 | Number 2 | June 2007 | Pages 267-279
Technical Note | doi.org/10.13182/NSE07-A2701
NEPTUNE: A New Software Platform for Advanced Nuclear Thermal Hydraulics
Antoine Guelfi, Dominique Bestion, Marc Boucker, Pascal Boudier, Philippe Fillion, Marc Grandotto, Jean-Marc Hérard, Eric Hervieu, Pierre Péturaud
Nuclear Science and Engineering | Volume 156 | Number 3 | July 2007 | Pages 281-324
Technical Paper | doi.org/10.13182/NSE05-98
Spatial Finite-Element Lumping Techniques for the Quadrilateral Mesh Sn Equations in X-Y Geometry
Jim E. Morel, James S. Warsa
Nuclear Science and Engineering | Volume 156 | Number 3 | July 2007 | Pages 325-342
Technical Paper | doi.org/10.13182/NSE06-13
Analytical Calculation of the Average Dancoff Factor for Prismatic High-Temperature Reactors
Alberto Talamo
Nuclear Science and Engineering | Volume 156 | Number 3 | July 2007 | Pages 343-356
Technical Paper | doi.org/10.13182/NSE07-A2704
New Nuclear Data Libraries for Lead and Bismuth and Their Impact on Accelerator-Driven Systems Design
A. J. Koning, M. C. Duijvestijn, S. C. van der Marck, R. Klein Meulekamp, A. Hogenbirk
Nuclear Science and Engineering | Volume 156 | Number 3 | July 2007 | Pages 357-390
Technical Paper | doi.org/10.13182/NSE156-357
Evaluation of the 238U Neutron Cross Section in the Unresolved Resonance Range
Arnaud Courcelle, Hervé Derrien, Luiz C. Leal, Nancy M. Larson
Nuclear Science and Engineering | Volume 156 | Number 3 | July 2007 | Pages 391-402
Technical Paper | doi.org/10.13182/NSE07-A2706
Unbiased Monte Carlo Estimation of the Reciprocal of an Integral
Thomas E. Booth
Nuclear Science and Engineering | Volume 156 | Number 3 | July 2007 | Pages 403-407
Technical Paper | doi.org/10.13182/NSE07-A2707
The Common Properties of the "Fertile" Isotopes
Y. Ronen
Nuclear Science and Engineering | Volume 156 | Number 3 | July 2007 | Pages 408-409
Technical Note | doi.org/10.13182/NSE07-A2708
