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The mission of the Decommissioning and Environmental Sciences (DES) Division is to promote the development and use of those skills and technologies associated with the use of nuclear energy and the optimal management and stewardship of the environment, sustainable development, decommissioning, remediation, reutilization, and long-term surveillance and maintenance of nuclear-related installations, and sites. The target audience for this effort is the membership of the Division, the Society, and the public at large.
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Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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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Senate committee hears from energy secretary nominee Chris Wright
Wright
Chris Wright, president-elect Trump’s pick to lead the U.S. Department of Energy, spent hours today fielding questions from members of the U.S. Senate’s committee on Energy and Natural Resources.
During the hearing, Wright—who’s spent most of his career in fossil fuels—made comments in support of nuclear energy and efforts to expand domestic generation in the near future. Asked what actions he would take as energy secretary to improve the development and deployment of SMRs, Wright said: “It’s a big challenge, and I’m new to government, so I can’t list off the five levers I can pull. But (I’ve been in discussions) about how to make it easier to research, to invest, to build things. The DOE has land at some of its facilities that can be helpful in this regard.”
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Calculation and Evaluation of Cross Sections and Kerma Factors for Neutrons up to 100 MeV on 16O and 14N
M. B. Chadwick, P. G. Young
Nuclear Science and Engineering | Volume 123 | Number 1 | May 1996 | Pages 1-16
Technical Paper | doi.org/10.13182/NSE96-A24209
Calculation and Evaluation of Cross Sections and Kerma Factors for Neutrons up to 100 MeV on Carbon
M. B. Chadwick, L. J. Cox, P. G. Young, A.S. Meigooni
Nuclear Science and Engineering | Volume 123 | Number 1 | May 1996 | Pages 17-37
Technical Paper | doi.org/10.13182/NSE96-A24210
The Even-Parity and Simplified Even-Parity Transport Equations in Two-Dimensional x-y Geometry
Taewan Noh, Warren F. Miller, Jr., Jim E. Morel
Nuclear Science and Engineering | Volume 123 | Number 1 | May 1996 | Pages 38-56
Technical Paper | doi.org/10.13182/NSE96-A24211
A Locally Exact Numerical Scheme with Nonoscillation Properties for Stationary Transport Equations with Absorption and Source Terms
Katsuhiro Sakai
Nuclear Science and Engineering | Volume 123 | Number 1 | May 1996 | Pages 57-67
Technical Paper | doi.org/10.13182/NSE96-A24212
Singular Perturbation Solutions of the Neutron Transport Equation
David C. Losey, John C. Lee, William R. Martin, Thomas C. Adamson, Jr.
Nuclear Science and Engineering | Volume 123 | Number 1 | May 1996 | Pages 68-85
Technical Paper | doi.org/10.13182/NSE96-A24213
The FLEXBURN Neutron Transport Code Developed by the Sn Method with Transmission Probabilities in Arbitrary Square Meshes for Light Water Reactor Fuel Assemblies
Takanori Kameyama, Tetsuo Matsumura, Makoto Sasak
Nuclear Science and Engineering | Volume 123 | Number 1 | May 1996 | Pages 86-95
Technical Paper | doi.org/10.13182/NSE96-A24214
Continuous Energy Monte Carlo Calculations of Randomly Distributed Spherical Fuels in High-Temperature Gas-Cooled Reactors Based on a Statistical Geometry Model
Isao Murata, Takamasa Mori, Masayuki Nakagawa
Nuclear Science and Engineering | Volume 123 | Number 1 | May 1996 | Pages 96-109
Technical Paper | doi.org/10.13182/NSE96-A24215
The Two-Region Milne Problem
B.D. Ganapol, G. C. Pomraning
Nuclear Science and Engineering | Volume 123 | Number 1 | May 1996 | Pages 110-120
Technical Paper | doi.org/10.13182/NSE96-A24216
The Effective Fuel Temperature to be Used for Calculating Resonance Absorption in a 238UO2 Lump with a Nonuniform Temperature Profile
W. J. M. de Kruijf, A. J. Janssen
Nuclear Science and Engineering | Volume 123 | Number 1 | May 1996 | Pages 121-135
Technical Paper | doi.org/10.13182/NSE94-108
The Effect of Gas Injection Configuration on Two-Phase Countercurrent Flow Limitation in Short Vertical Channels
S. M. Ghiaasiaan, J. D. Bohner, S. I. Abdel-Khalik
Nuclear Science and Engineering | Volume 123 | Number 1 | May 1996 | Pages 136-146
Technical Paper | doi.org/10.13182/NSE96-A24218
An Upwind Numerical Method for Two-Fluid Two-Phase Flow Models
I. Toumi
Nuclear Science and Engineering | Volume 123 | Number 2 | June 1996 | Pages 147-168
Technical Paper | doi.org/10.13182/NSE96-A24180
Numerical Simulations of Nonstationary Fronts and Interfaces by the Godunov Method in Moving Grids
V. E. Fortov, B. Goel, C.-D. Munz, A. L. Ni, A. V. Shutov, O. Yu. Vorobiev
Nuclear Science and Engineering | Volume 123 | Number 2 | June 1996 | Pages 169-189
Technical Paper | doi.org/10.13182/NSE96-A24181
Evaluation of Inherent Distortions in the IIST Facility Using the RELAP5/MOD3 Code
Yuh-Ming Ferng
Nuclear Science and Engineering | Volume 123 | Number 2 | June 1996 | Pages 190-205
Technical Paper | doi.org/10.13182/NSE96-A24182
A Second-Derivative-Based Adaptive Time-Step Method for Spatial Kinetics Calculations
Nicolas Crouzet, Paul J. Turinsky
Nuclear Science and Engineering | Volume 123 | Number 2 | June 1996 | Pages 206-214
Technical Paper | doi.org/10.13182/NSE96-A24183
Improvement of Gamma-Ray Sn Transport Calculations Including Coherent and Incoherent Scatterings and Secondary Sources of Bremsstrahlung and Fluorescence: Determination of Gamma-Ray Buildup Factors
P. Ridoux, S. Kitsos, C. M. Diop, A. Assad, J. C. Nimal
Nuclear Science and Engineering | Volume 123 | Number 2 | June 1996 | Pages 215-227
Technical Paper | doi.org/10.13182/NSE96-A24184
Inconsistencies in Widely Used Monte Carlo Methods for Precise Calculation of Radial Resonance Captures in Uranium Fuel Rods
Donald Bogart
Nuclear Science and Engineering | Volume 123 | Number 2 | June 1996 | Pages 228-237
Technical Paper | doi.org/10.13182/NSE96-A24185
The Accident Sequence Precursor Analysis: Review of the Methods and New Insights
M. Modarres, H. Martz, M. Kaminskiy
Nuclear Science and Engineering | Volume 123 | Number 2 | June 1996 | Pages 238-258
Technical Paper | doi.org/10.13182/NSE96-A24186
A Method for Measurement of Delayed Neutron Parameters for Liquid-Metal-Cooled Power Reactors
Richard B. Vilim, Richard W. Brock
Nuclear Science and Engineering | Volume 123 | Number 2 | June 1996 | Pages 259-271
Technical Paper | doi.org/10.13182/NSE96-A24187
Benchmark Test of 14-MeV Neutron-Induced Gamma-Ray Production Data in JENDL-3.2 and FENDL/E-1.0 Through Analysis of the OKTAVIAN Experiments
F. Maekawa, Y. Oyama
Nuclear Science and Engineering | Volume 123 | Number 2 | June 1996 | Pages 272-281
Technical Paper | doi.org/10.13182/NSE96-A24188
Skyshine Line-Beam Response Functions for 20- to 100-MeV Photons
R. C. Brockhoff, J. Kenneth Shultis, Richard E. Faw
Nuclear Science and Engineering | Volume 123 | Number 2 | June 1996 | Pages 282-288
Technical Paper | doi.org/10.13182/NSE96-A24189
Effect of an Overhead Shield on Gamma-Ray Skyshine
Mark H. Stedry, J. Kenneth Shultis, Richard E. Faw
Nuclear Science and Engineering | Volume 123 | Number 2 | June 1996 | Pages 289-294
Technical Paper | doi.org/10.13182/NSE96-A24190
Modeling Water Chemistry, Electrochemical Corrosion Potential, and Crack Growth Rate in the Boiling Water Reactor Heat Transport Circuits—II: Simulation of Operating Reactors
Tsung-Kuang Yeh, Digby D. Macdonald
Nuclear Science and Engineering | Volume 123 | Number 2 | June 1996 | Pages 295-304
Technical Paper | doi.org/10.13182/NSE96-A24191
Modeling Water Chemistry, Electrochemical Corrosion Potential, and Crack Growth Rate in the Boiling Water Reactor Heat Transport Circuits —III: Effect of Reactor Power Level
Nuclear Science and Engineering | Volume 123 | Number 2 | June 1996 | Pages 305-316
Technical Paper | doi.org/10.13182/NSE96-A24192
A Three-Dimensional Time-Dependent Unstructured Tetrahedral-Mesh SPN Method
J. E. Morel,J. M. McGhee,Edward W. Larsen
Nuclear Science and Engineering | Volume 123 | Number 3 | July 1996 | Pages 319-327
Technical Paper | doi.org/10.13182/NSE96-A24196
Asymptotic Derivation of the Multigroup P1 and Simplified PN Equations with Anisotropic Scattering
Edward W. Larsen, J. E. Morel, John M. McGhee
Nuclear Science and Engineering | Volume 123 | Number 3 | July 1996 | Pages 328-342
Technical Paper | doi.org/10.13182/NSE123-328
Asymptotic Derivation of the Fermi Pencil-Beam Approximation
Christoph Börgers,Edward W. Larsen
Nuclear Science and Engineering | Volume 123 | Number 3 | July 1996 | Pages 343-357
Technical Paper | doi.org/10.13182/NSE96-A24198
Application of the BnTheory to Unit Cell Calculations
R. Roy
Nuclear Science and Engineering | Volume 123 | Number 3 | July 1996 | Pages 358-368
Technical Paper | doi.org/10.13182/NSE96-A24199
Variational Nodal Transport Perturbation Theory
Kirsten F. Laurin-Kovitz,E. E. Lewis
Nuclear Science and Engineering | Volume 123 | Number 3 | July 1996 | Pages 369-380
Technical Paper | doi.org/10.13182/NSE96-A24200
Solution of Mathematical Adjoint Equation for a Higher Order Nodal Expansion Method
Taek Kyum Kim, Chang Hyo Kim
Nuclear Science and Engineering | Volume 123 | Number 3 | July 1996 | Pages 381-391
Technical Paper | doi.org/10.13182/NSE96-A24201
Collision Probability Calculation and Multigroup Flux Solvers Using PVM
A. Qaddouri, R. Roy, M. Mayrand, B. Goulard
Nuclear Science and Engineering | Volume 123 | Number 3 | July 1996 | Pages 392-402
Technical Paper | doi.org/10.13182/NSE96-A24202
An Incomplete Domain Decomposition Preconditioning Method for Nonlinear Nodal Kinetics Calculations
Han Gyu Joo,Thomas J. Downar
Nuclear Science and Engineering | Volume 123 | Number 3 | July 1996 | Pages 403-414
Technical Paper | doi.org/10.13182/NSE96-A24203
A Domain Decomposition Method for Nonlinear Steady-State Flow Computations
Sébastien Clerc
Nuclear Science and Engineering | Volume 123 | Number 3 | July 1996 | Pages 415-420
Technical Paper | doi.org/10.13182/NSE96-A24204
Moving-Particle Semi-Implicit Method for Fragmentation of Incompressible Fluid
S. Koshizuka, Y. Oka
Nuclear Science and Engineering | Volume 123 | Number 3 | July 1996 | Pages 421-434
Technical Paper | doi.org/10.13182/NSE96-A24205
Kalman Filter Application for Distributed Parameter Estimation in Reactor Systems
Robert P. Martin, Robert M. Edwards
Nuclear Science and Engineering | Volume 123 | Number 3 | July 1996 | Pages 435-442
Technical Paper | doi.org/10.13182/NSE96-A24206
Flow Modeling in Heterogeneous Media in the Context of Geologic Nuclear Waste Repositories
Budhi Sagar
Nuclear Science and Engineering | Volume 123 | Number 3 | July 1996 | Pages 443-454
Technical Paper | doi.org/10.13182/NSE96-A24207
