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The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
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Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
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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
