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Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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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ARG-US Remote Monitoring Systems: Use Cases and Applications in Nuclear Facilities and During Transportation
As highlighted in the Spring 2024 issue of Radwaste Solutions, researchers at the Department of Energy’s Argonne National Laboratory are developing and deploying ARG-US—meaning “Watchful Guardian”—remote monitoring systems technologies to enhance the safety, security, and safeguards (3S) of packages of nuclear and other radioactive material during storage, transportation, and disposal.
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A Multilevel Projective Method for Solving the Space-Time Multigroup Neutron Kinetics Equations Coupled with the Heat Transfer Equation
Apil Tamang, Dmitriy Y. Anistratov
Nuclear Science and Engineering | Volume 177 | Number 1 | May 2014 | Pages 1-18
Technical Paper | doi.org/10.13182/NSE13-42
On PN Interface and Boundary Conditions
Richard Sanchez
Nuclear Science and Engineering | Volume 177 | Number 1 | May 2014 | Pages 19-34
Technical Paper | doi.org/10.13182/NSE12-95
The Analytical Discrete Ordinates Method for a One-Dimensional Model of Neutral Particle Transport in Ducts
R. D. M. Garcia
Nuclear Science and Engineering | Volume 177 | Number 1 | May 2014 | Pages 35-51
Technical Paper | doi.org/10.13182/NSE13-45
Iterative Determination of Distributions by the Monte Carlo Method in Problems with an External Source
Mihály Makai, Zoltán Szatmáry
Nuclear Science and Engineering | Volume 177 | Number 1 | May 2014 | Pages 52-67
Technical Paper | doi.org/10.13182/NSE12-97
Kinematics of the 6Li(n,t)4He Reaction and Experimental Scenarios for Cross-Section Measurement
R. Bencardino, R. Bevilacqua, G. Giorginis, F.-J. Hambsch
Nuclear Science and Engineering | Volume 177 | Number 1 | May 2014 | Pages 68-76
Technical Paper | doi.org/10.13182/NSE13-25
Target Motion Sampling Temperature Treatment Technique with Elevated Basis Cross-Section Temperatures
Tuomas Viitanen, Jaakko Leppänen
Nuclear Science and Engineering | Volume 177 | Number 1 | May 2014 | Pages 77-89
Technical Paper | doi.org/10.13182/NSE13-37
Neutron Cross-Section Covariances in the Resolved Resonance Region for 55Mn
Young-Sik Cho, Young-Ouk Lee
Nuclear Science and Engineering | Volume 177 | Number 1 | May 2014 | Pages 90-96
Technical Paper | doi.org/10.13182/NSE12-96
Possible Design of Long-Life Small Prismatic HTGR for Passive Decay Heat Removal
Odmaa Sambuu, Toru Obara
Nuclear Science and Engineering | Volume 177 | Number 1 | May 2014 | Pages 97-110
Technical Note | doi.org/10.13182/NSE13-22
Massively Parallel, Three-Dimensional Transport Solutions for the k-Eigenvalue Problem
Gregory G. Davidson, Thomas M. Evans, Joshua J. Jarrell, Steven P. Hamilton, Tara M. Pandya, Rachel N. Slaybaugh
Nuclear Science and Engineering | Volume 177 | Number 2 | June 2014 | Pages 111-125
Technical Paper | doi.org/10.13182/NSE12-101
Transport Theory–Based Analog Monte Carlo for Simulating Noise Experiments in Subcritical Systems
K. P. Singh, S. B. Degweker
Nuclear Science and Engineering | Volume 177 | Number 2 | June 2014 | Pages 126-140
Technical Paper | doi.org/10.13182/NSE13-39
Examination of Separate-Effect and Integral Phenomena Within a Grid Spacer With Mixing Vanes: Results for the MATiS-H OECD/NEA Benchmark Exercise
A. Rashkovan, D. McClure, D. R. Novog
Nuclear Science and Engineering | Volume 177 | Number 2 | June 2014 | Pages 141-155
Technical Paper | doi.org/10.13182/NSE13-4
Mockup Experiments on the Thorium-Loaded Accelerator-Driven System at the Kyoto University Critical Assembly
Cheol Ho Pyeon, Takahiro Yagi, Kiichi Sukawa, Yoshimasa Yamaguchi, Tsuyoshi Misawa
Nuclear Science and Engineering | Volume 177 | Number 2 | June 2014 | Pages 156-168
Technical Paper | doi.org/10.13182/NSE13-21
Initiation of Persistent Fission Chains in the Fast Burst Reactor Caliban
Nicolas Authier, Benoît Richard, Philippe Humbert
Nuclear Science and Engineering | Volume 177 | Number 2 | June 2014 | Pages 169-183
Technical Paper | doi.org/10.13182/NSE12-111
Monte Carlo Fuel Temperature Coefficient Estimation by an Adjoint-Weighted Correlated Sampling Method
Hyung Jin Shim, Chang Hyo Kim
Nuclear Science and Engineering | Volume 177 | Number 2 | June 2014 | Pages 184-192
Technical Paper | doi.org/10.13182/NSE13-29
Internal Neutronics-Temperature Coupling in Serpent 2
Ville Valtavirta, Tuomas Viitanen, Jaakko Leppänen
Nuclear Science and Engineering | Volume 177 | Number 2 | June 2014 | Pages 193-202
Technical Paper | doi.org/10.13182/NSE13-3
Calculation of the Neutron Noise Induced by Periodic Deformations of a Large Sodium-Cooled Fast Reactor Core
F. Zylbersztejn, H. N. Tran, I. Pázsit, P. Filliatre, C. Jammes
Nuclear Science and Engineering | Volume 177 | Number 2 | June 2014 | Pages 203-218
Technical Paper | doi.org/10.13182/NSE13-41
Radiative Capture Cross Sections of 155,157Gd for Thermal Neutrons
H. D. Choi, R. B. Firestone, M. S. Basunia, A. Hurst, B. Sleaford, N. Summers, J. E. Escher, Zs. Révay, L. Szentmiklósi, T. Belgya, M. Krtička
Nuclear Science and Engineering | Volume 177 | Number 2 | June 2014 | Pages 219-232
Technical Paper | doi.org/10.13182/NSE13-49
A Point Kinetics Model of the Medical Isotope Production Reactor Including the Effects of Boiling
C. M. Cooling, M. M. R. Williams, E. T. Nygaard, M. D. Eaton
Nuclear Science and Engineering | Volume 177 | Number 3 | July 2014 | Pages 233-259
Technical Paper | doi.org/10.13182/NSE13-55
Control Rod Depletion in Sodium-Cooled Fast Reactor: Models and Impact on Reactivity Control
David Blanchet, Bruno Fontaine
Nuclear Science and Engineering | Volume 177 | Number 3 | July 2014 | Pages 260-274
Technical Paper | doi.org/10.13182/NSE13-59
Validation Study of Pin Heat Transfer for UO2 Fuel Based on the IFA-432 Experiments
Aaron M. Phillippe, James E. Banfield, Kevin T. Clarno, Larry J. Ott, Bobby Philip, Mark A. Berrill, Rahul S. Sampath, Srikanth Allu, Steven P. Hamilton
Nuclear Science and Engineering | Volume 177 | Number 3 | July 2014 | Pages 275-290
Technical Paper | doi.org/10.13182/NSE13-18
Inventory Simulations Under Neutron Irradiation: Visualization Techniques as an Aid to Materials Design
M. R. Gilbert, L. W. Packer, J.-Ch. Sublet, R. A. Forrest
Nuclear Science and Engineering | Volume 177 | Number 3 | July 2014 | Pages 291-306
Technical Paper | doi.org/10.13182/NSE13-76
Smoothing and Time Series Modeling of Nuclear Material Accounting Data for Protracted Diversion Detection
Tom Burr, Michael S. Hamada
Nuclear Science and Engineering | Volume 177 | Number 3 | July 2014 | Pages 307-320
Technical Paper | doi.org/10.13182/NSE13-86
UO2 Versus MOX: Propagated Nuclear Data Uncertainty for keff, with Burnup
Petter Helgesson, Dimitri Rochman, Henrik Sjöstrand, Erwin Alhassan, Arjan Koning
Nuclear Science and Engineering | Volume 177 | Number 3 | July 2014 | Pages 321-336
Technical Paper | doi.org/10.13182/NSE13-48
Efficient Use of Monte Carlo: Uncertainty Propagation
D. Rochman, W. Zwermann, S. C. van der Marck, A. J. Koning, H. Sjöstrand, P. Helgesson, B. Krzykacz-Hausmann
Nuclear Science and Engineering | Volume 177 | Number 3 | July 2014 | Pages 337-349
Technical Paper | doi.org/10.13182/NSE13-32
High-Dimensional Model Representations for the Neutron Transport Equation
Zhengzheng Hu, Ralph C. Smith, Jeffrey Willert, C. T. Kelley
Nuclear Science and Engineering | Volume 177 | Number 3 | July 2014 | Pages 350-360
Technical Paper | doi.org/10.13182/NSE13-52
Analysis of Example Problems for Monte Carlo Surface Flux Tallies
Jeffrey A. Favorite
Nuclear Science and Engineering | Volume 177 | Number 3 | July 2014 | Pages 361-366
Technical Note | doi.org/10.13182/NSE13-66
