ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Division Spotlight
Isotopes & Radiation
Members are devoted to applying nuclear science and engineering technologies involving isotopes, radiation applications, and associated equipment in scientific research, development, and industrial processes. Their interests lie primarily in education, industrial uses, biology, medicine, and health physics. Division committees include Analytical Applications of Isotopes and Radiation, Biology and Medicine, Radiation Applications, Radiation Sources and Detection, and Thermal Power Sources.
Meeting Spotlight
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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!
Latest Magazine Issues
Apr 2024
Jan 2024
Latest Journal Issues
Nuclear Science and Engineering
May 2024
Nuclear Technology
Fusion Science and Technology
Latest News
College students help develop waste-measuring device at Hanford
A partnership between Washington River Protection Solutions (WRPS) and Washington State University has resulted in the development of a device to measure radioactive and chemical tank waste at the Hanford Site. WRPS is the contractor at Hanford for the Department of Energy’s Office of Environmental Management.
Jump to:
The Pencil Beam Problem for Screened Rutherford Scattering
G. C. Pomraning, Anil K. Prinja
Nuclear Science and Engineering | Volume 130 | Number 1 | September 1998 | Pages 1-17
Technical Paper | doi.org/10.13182/NSE98-A1986
Characteristic Methods in Thick Diffusive Problems
Marvin L. Adams, Todd A. Wareing, Wallace F. Walters
Nuclear Science and Engineering | Volume 130 | Number 1 | September 1998 | Pages 18-46
Technical Paper | doi.org/10.13182/NSE98-A1987
Stabilization Techniques for the Nonlinear Analytic Nodal Method
Han Gyu Joo, Guobing Jiang, Thomas J. Downar
Nuclear Science and Engineering | Volume 130 | Number 1 | September 1998 | Pages 47-59
Technical Paper | doi.org/10.13182/NSE98-A1988
A PN Solution to the Multigroup Slowing-Down Problem - I: Basic Formulation
A. D. Caldeira, A. F. Dias, R. D. M. Garcia
Nuclear Science and Engineering | Volume 130 | Number 1 | September 1998 | Pages 60-69
Technical Paper | doi.org/10.13182/NSE98-A1989
A PN Solution to the Multigroup Slowing-Down Problem - II: The Degenerate Case
Nuclear Science and Engineering | Volume 130 | Number 1 | September 1998 | Pages 70-78
Technical Paper | doi.org/10.13182/NSE98-A1990
On the Equivalence Between the Discrete Ordinates and the Spherical Harmonics Methods in Radiative Transfer
L. B. Barichello, C. E. Siewert
Nuclear Science and Engineering | Volume 130 | Number 1 | September 1998 | Pages 79-84
Technical Paper | doi.org/10.13182/NSE98-A1991
The Stochastic Behavior of the Eigenvalue Due to Spatial Perturbation in the Fuel Distribution of the One-Speed Slab Reactor
Salim N. Jahshan
Nuclear Science and Engineering | Volume 130 | Number 1 | September 1998 | Pages 85-97
Technical Paper | doi.org/10.13182/NSE98-A1992
Higher Order Generalized Perturbation Theory for Boiling Water Reactor In-Core Fuel Management Optimization
Brian R. Moore, Paul J. Turinsky
Nuclear Science and Engineering | Volume 130 | Number 1 | September 1998 | Pages 98-112
Technical Paper | doi.org/10.13182/NSE98-A1993
On-Line Estimation of Transit Time Using Artificial Neural Networks
T. Tambouratzis, M. Antonopoulos-Domis, M. Marseguerra, E. Padovani
Nuclear Science and Engineering | Volume 130 | Number 1 | September 1998 | Pages 113-127
Technical Paper | doi.org/10.13182/NSE98-A1994
Pressurized Water Reactor Reload Design by an Expert System
Kuan-Jan Lin, Chaung Lin
Nuclear Science and Engineering | Volume 130 | Number 1 | September 1998 | Pages 128-140
Technical Paper | doi.org/10.13182/NSE98-A1995
Passive Neutron Assay of Plutonium Materials: Monte Carlo Procedures to Simulate Generation of Neutron Pulse Trains and the Application of the Neutron Coincidence Counting Method
A. Dodaro, F. V. Frazzoli, R. Remetti
Nuclear Science and Engineering | Volume 130 | Number 1 | September 1998 | Pages 141-152
Technical Paper | doi.org/10.13182/NSE98-A1996
The Central Void Reactivity in the Oak Ridge National Laboratory Enriched Uranium (93.2) Metal Sphere
J. T. Mihalczo, J. J. Lynn, J. R. Taylor
Nuclear Science and Engineering | Volume 130 | Number 1 | September 1998 | Pages 153-163
Technical Paper | doi.org/10.13182/NSE96-121
Experimental Determination and Simulation of the Reactivity Effects and Reaction Rate Sensitivity to Different Ranges of Neutron Energy in Homogeneous Heavy Water Solutions of Thorium
Yu. E. Titarenko, O. V. Shvedov, M. M. Igumnov, E. I. Karpikhin, V. F. Batyaev, A. V. Lopatkin, V. I. Volk, A. Yu. Vakhrushin, S. V. Shepelkov, S. G. Mashnik, T. A. Gabriel
Nuclear Science and Engineering | Volume 130 | Number 2 | October 1998 | Pages 165-180
Technical Paper | doi.org/10.13182/NSE98-A1998
Red-Black Response Matrix Acceleration by Transformation of Interface Variables
E. E. Lewis, G. Palmiotti
Nuclear Science and Engineering | Volume 130 | Number 2 | October 1998 | Pages 181-193
Technical Paper | doi.org/10.13182/NSE98-A1999
The FN Method for Multigroup Transport Theory with Upscattering
R. D. M. Garcia, C. E. Siewert
Nuclear Science and Engineering | Volume 130 | Number 2 | October 1998 | Pages 194-212
Technical Paper | doi.org/10.13182/NSE98-A2000
An Implicit Second-Order Numerical Method for Three-Dimensional Two-Phase Flow Calculations
I. Toumi, D. Caruge
Nuclear Science and Engineering | Volume 130 | Number 2 | October 1998 | Pages 213-225
Technical Paper | doi.org/10.13182/NSE98-A2001
Transfer Matrix Treatments in TRIMARAN-II, Nonequally Probable Step Function Representation in Multigroup Monte Carlo
Li Mao, J. P. Both, J. C. Nimal
Nuclear Science and Engineering | Volume 130 | Number 2 | October 1998 | Pages 226-238
Technical Paper | doi.org/10.13182/NSE98-A2002
A High-Conversion Water Reactor Design
Y. Ronen, Y. Dali
Nuclear Science and Engineering | Volume 130 | Number 2 | October 1998 | Pages 239-253
Technical Paper | doi.org/10.13182/NSE98-A2003
(n,) Reaction Cross Sections of 44Ca, 45Sc, and 51V Nuclei from 13.6 to 14.9 MeV
M. Subasi, M. N. Erduran, M. Bostan, I. A. Reyhancan, E. Gültekin, G. Tarcan, Y. Ozbir, A. Durusoy
Nuclear Science and Engineering | Volume 130 | Number 2 | October 1998 | Pages 254-260
Technical Paper | doi.org/10.13182/NSE98-A2004
Improvements in the Theory of Identification of Burst-Shaped Events for Fault Diagnosis
G. Szappanos, G. Por
Nuclear Science and Engineering | Volume 130 | Number 2 | October 1998 | Pages 261-267
Technical Note | doi.org/10.13182/NSE98-A2005
A Kinetic Theory for Nonanalog Monte Carlo Algorithms: Exponential Transform with Angular Biasing
Taro Ueki, Edward W. Larsen
Nuclear Science and Engineering | Volume 130 | Number 3 | November 1998 | Pages 269-291
Technical Paper | doi.org/10.13182/NSE98-A2006
A Probabilistic Method for On-Line Response Prediction of Uncertain and Dynamic Systems
R. B. Vilim
Nuclear Science and Engineering | Volume 130 | Number 3 | November 1998 | Pages 292-308
Technical Paper | doi.org/10.13182/NSE98-A2007
The Transmutation of Long-Lived Fission Products by Neutron Irradiation
M. Salvatores, I. Slessarev, A. Tchistiakov
Nuclear Science and Engineering | Volume 130 | Number 3 | November 1998 | Pages 309-319
Technical Paper | doi.org/10.13182/NSE98-A2008
Activation by Protons in Range-Thick Lead and Tungsten Spallation Targets
C. E. Laird, D. H. Mullins, D. B. McGibney, John Swartz, R. W. Kamau, C. L. Snead, M. S. Zucker, T. E. Ward, E. M. Franz, G. A. Greene
Nuclear Science and Engineering | Volume 130 | Number 3 | November 1998 | Pages 320-339
Technical Paper | doi.org/10.13182/NSE98-A2009
Justification of a Simple Ramsauer Model for Neutron Total Cross Sections
S. M. Grimes, J. D. Anderson, R. W. Bauer, V. A. Madsen
Nuclear Science and Engineering | Volume 130 | Number 3 | November 1998 | Pages 340-347
Technical Paper | doi.org/10.13182/NSE98-A2010
Application of a Simple Ramsauer Model for Neutron Total Cross Sections
R. W. Bauer, J. D. Anderson, S. M. Grimes, D. A. Knapp, V. A. Madsen
Nuclear Science and Engineering | Volume 130 | Number 3 | November 1998 | Pages 348-360
Technical Paper | doi.org/10.13182/NSE98-A2011
A Computational Fluid Dynamics and Heat Transfer Model for Gaseous Core and Very High Temperature Gas-Cooled Reactors
Samim Anghaie, Gary Chen
Nuclear Science and Engineering | Volume 130 | Number 3 | November 1998 | Pages 361-373
Technical Paper | doi.org/10.13182/NSE98-A2012
Monte Carlo Estimates of Transport Solutions to the Isotropic Slab Problem
Thomas E. Booth
Nuclear Science and Engineering | Volume 130 | Number 3 | November 1998 | Pages 374-385
Technical Note | doi.org/10.13182/NSE98-A2013
Effect of Low-Energy Resonance Absorber on Positive Neutron Temperature Coefficient of Dilute Plutonium-Water Solution
Toru Obara, Hiroshi Sekimoto
Nuclear Science and Engineering | Volume 130 | Number 3 | November 1998 | Pages 386-390
Technical Note | doi.org/10.13182/NSE98-A2014