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Division Spotlight
Young Members Group
The Young Members Group works to encourage and enable all young professional members to be actively involved in the efforts and endeavors of the Society at all levels (Professional Divisions, ANS Governance, Local Sections, etc.) as they transition from the role of a student to the role of a professional. It sponsors non-technical workshops and meetings that provide professional development and networking opportunities for young professionals, collaborates with other Divisions and Groups in developing technical and non-technical content for topical and national meetings, encourages its members to participate in the activities of the Groups and Divisions that are closely related to their professional interests as well as in their local sections, introduces young members to the rules and governance structure of the Society, and nominates young professionals for awards and leadership opportunities available to members.
Meeting Spotlight
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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Latest News
Grant awarded for advanced reactor workforce needs in southeast U.S.
North Carolina State University and the Electric Power Research Institute have been awarded a $500,000 grant by the NC Collaboratory for “An Assessment to Define Advanced Reactor Workforce Needs,” a project that aims to investigate job needs to help enable new nuclear development and deployment in North Carolina and surrounding areas.
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Biases in Monte Carlo Eigenvalue Calculations
Ely M. Gelbard, Albert G. Gu
Nuclear Science and Engineering | Volume 117 | Number 1 | May 1994 | Pages 1-9
Technical Paper | doi.org/10.13182/NSE94-A13564
Importance Iteration in MORSE Monte Carlo Calculations
J. L. Kloosterman, J. E. Hoogenboom
Nuclear Science and Engineering | Volume 117 | Number 1 | May 1994 | Pages 10-21
Technical Paper | doi.org/10.13182/NSE94-A13565
Modeling of Gravity-Driven Oscillatory Countercurrent Two-Phase Channel Flows
S. M. Ghiaasiaan, B. K. Kamboj, S. I. Abdel-Khalik
Nuclear Science and Engineering | Volume 117 | Number 1 | May 1994 | Pages 22-32
Technical Paper | doi.org/10.13182/NSE94-A13566
Thermal and Stability Analysis of a Two-Phase Natural Circulation Loop
Fu-Shin Wang, Lin-Wen Hu, Chin Pan
Nuclear Science and Engineering | Volume 117 | Number 1 | May 1994 | Pages 33-46
Technical Paper | doi.org/10.13182/NSE94-A13567
Determination of Point Isotropic Buildup Factors of Gamma Rays Including Incoherent and Coherent Scattering for Aluminum, Iron, Lead, and Water by the Discrete Ordinates Method
S. Kitsos, A. Assad, C. M. Diop, J. C. Nimal, P. Ridoux
Nuclear Science and Engineering | Volume 117 | Number 1 | May 1994 | Pages 47-66
Technical Paper | doi.org/10.13182/NSE94-A13568
The 93Nb(n,xp) Reaction at En = 14.6 MeV
Bangjiao Ye, Yangmei Fan, Zhongmin Wang, Rongdian Han, Zhenxi Xiao
Nuclear Science and Engineering | Volume 117 | Number 1 | May 1994 | Pages 67-75
Technical Paper | doi.org/10.13182/NSE94-A13569
Powerful Hard-Spectrum Neutrino Source Based on Lithium Converter of Reactor Neutrons to Antineutrinos
Yu. S. Lyutostansky, V. I. Lyashuk
Nuclear Science and Engineering | Volume 117 | Number 2 | June 1994 | Pages 77-87
Technical Paper | doi.org/10.13182/NSE94-A20074
Nucleon Double-Differential Cross Section Based on Anisotropic Intranuclear Scattering
Qingbiao Shen, Jingshang Zhang
Nuclear Science and Engineering | Volume 117 | Number 2 | June 1994 | Pages 88-98
Technical Paper | doi.org/10.13182/NSE94-A20075
Double-Differential Cross Section of Light Composite Particles in the Exciton Model
Qingbiao Shen
Nuclear Science and Engineering | Volume 117 | Number 2 | June 1994 | Pages 99-109
Technical Paper | doi.org/10.13182/NSE93-66
The Use of an Expanded Polynomial Orthogonal Set in Approximations to Gamma-Ray Buildup Factor Data
Ivan Michieli
Nuclear Science and Engineering | Volume 117 | Number 2 | June 1994 | Pages 110-120
Technical Paper | doi.org/10.13182/NSE94-A20077
Solution of Depletion Chain Equations Using Nonsingular Bateman Coefficients
Zoran Vukadin
Nuclear Science and Engineering | Volume 117 | Number 2 | June 1994 | Pages 121-125
Technical Paper | doi.org/10.13182/NSE94-A20078
Countercurrent Gas-Liquid Flow in a Pressurized Water Reactor Hot Leg
Martin Lopez de Bertodano
Nuclear Science and Engineering | Volume 117 | Number 2 | June 1994 | Pages 126-133
Technical Paper | doi.org/10.13182/NSE94-A20079
Impurity Characterization of Si1−xGex Circuit Structures with the Use of Neutron Activation Analysis
S. C. McGuire,T. Z. Hossain, R. J. Soave
Nuclear Science and Engineering | Volume 117 | Number 2 | June 1994 | Pages 134-139
Technical Note | doi.org/10.13182/NSE94-A20080
Accounting for the Thermal Neutron Flux Depression in Voluminous Samples for Instrumental Neutron Activation Analysis
R. M. W. Overwater, J. E. Hoogenboom
Nuclear Science and Engineering | Volume 117 | Number 3 | July 1994 | Pages 141-157
Technical Paper | doi.org/10.13182/NSE94-A28530
KENO-NR: A Monte Carlo Code for Simulating 252Cf-Source-Driven Noise Measurements to Determine Subcriticality
Edward P. Ficaro, David K. Wehe
Nuclear Science and Engineering | Volume 117 | Number 3 | July 1994 | Pages 158-176
Technical Paper | doi.org/10.13182/NSE94-A28531
Robust Wide-Range Control of Nuclear Reactors by Using the Feedforward-Feedback Concept
Chen-Kuo Weng, Robert M. Edwards, Asok Ray
Nuclear Science and Engineering | Volume 117 | Number 3 | July 1994 | Pages 177-185
Technical Paper | doi.org/10.13182/NSE94-A28532
Reactivity Surveillance in a Nuclear Reactor by Using a Layered Artificial Neural Network
A. John Arul
Nuclear Science and Engineering | Volume 117 | Number 3 | July 1994 | Pages 186-193
Technical Paper | doi.org/10.13182/NSE94-A28533
Fault Diagnosis Via Neural Networks: The Boltzmann Machine
M. Marseguerra, E. Zio
Nuclear Science and Engineering | Volume 117 | Number 3 | July 1994 | Pages 194-200
Technical Paper | doi.org/10.13182/NSE94-A28534
Determination of the Double Angular and Energy Differential Gamma-Ray Albedo for Iron Material by Using the Monte Carlo Method
C. M. Diop, B. Elhamzaoui, J. C. Nimal
Nuclear Science and Engineering | Volume 117 | Number 4 | August 1994 | Pages 201-226
Technical Paper | doi.org/10.13182/NSE94-A21499
Monte Carlo Calculation of Dancoff Factors in Irregular Geometries
S.Fehér, J. E. Hoogenboom, P. F. A. de Leege, J. Valkó
Nuclear Science and Engineering | Volume 117 | Number 4 | August 1994 | Pages 227-238
Technical Paper | doi.org/10.13182/NSE94-A21500
Sensitivity, Uncertainty Assessment, and Target Accuracies Related to Radiotoxicity Evaluation
G. Palmiotti, M. Salvatores, R. N. Hill
Nuclear Science and Engineering | Volume 117 | Number 4 | August 1994 | Pages 239-250
Technical Paper | doi.org/10.13182/NSE94-A21501
Photon Interaction Cross Sections of Several Sugars for 137Cs and 60Co Photons
K. P. Gopinathan Nair, T. K. Umesh, Ramakrishna Gowda
Nuclear Science and Engineering | Volume 117 | Number 4 | August 1994 | Pages 251-253
Technical Paper | doi.org/10.13182/NSE94-A21502
Reduction of the Sodium Void Reactivity Effect by Using a 99Tc Layer
S.F. Kessler
Nuclear Science and Engineering | Volume 117 | Number 4 | August 1994 | Pages 254-258
Technical Note | doi.org/10.13182/NSE94-A21503
