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Fusion Energy
This division promotes the development and timely introduction of fusion energy as a sustainable energy source with favorable economic, environmental, and safety attributes. The division cooperates with other organizations on common issues of multidisciplinary fusion science and technology, conducts professional meetings, and disseminates technical information in support of these goals. Members focus on the assessment and resolution of critical developmental issues for practical fusion energy applications.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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
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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Weapons-Grade Plutonium Disposition in Pressurized Water Reactors
Debdas Biswas, Roy W. Rathbun, Si Young Lee, Melvin R. Buckner
Nuclear Science and Engineering | Volume 121 | Number 1 | September 1995 | Pages 1-16
Technical Paper | doi.org/10.13182/NSE95-A24124
Physics Studies of Weapons Plutonium Disposition in the Integral Fast Reactor Closed Fuel Cycle
R. N. Hill, D. C. Wade, J. R. Liaw, E. K. Fujita
Nuclear Science and Engineering | Volume 121 | Number 1 | September 1995 | Pages 17-31
Technical Paper | doi.org/10.13182/NSE121-17
Optimization of a Calculation Scheme for the Treatment of Plutonium Recycling in Pressurized Water Reactors
Philippe Fougeras, Stéphane Cathalau, Jacques Mondot, Pavel Klenov
Nuclear Science and Engineering | Volume 121 | Number 1 | September 1995 | Pages 32-40
Technical Paper | doi.org/10.13182/NSE121-32
CASMO-4/SIMULATE-3 Benchmarking Against High Plutonium Content Pressurized Water Reactor Mixed-Oxide Fuel Critical Experiment
Masaaki Mori and Mitsuru Kawamura, Koichi Yamate
Nuclear Science and Engineering | Volume 121 | Number 1 | September 1995 | Pages 41-51
Technical Paper | doi.org/10.13182/NSE95-A24127
Analyses of Boiling Water Reactor Mixed-Oxide Critical Experiments with CASMO-4/SIMULATE-3
E. Saji, H. Shirayanagi
Nuclear Science and Engineering | Volume 121 | Number 1 | September 1995 | Pages 52-56
Technical Paper | doi.org/10.13182/NSE95-A24128
Continuing Advancements in In-Core Power Distribution Measurement Methods Using SIMULATE-3 and CECOR 3.4
Charles F. Karlson
Nuclear Science and Engineering | Volume 121 | Number 1 | September 1995 | Pages 57-66
Technical Paper | doi.org/10.13182/NSE95-A24129
Optimization of Pressurized Water Reactor Shuffling by Simulated Annealing with Heuristics
J. G. Stevens, K. S. Smith, K. R. Rempe, T. J. Downar
Nuclear Science and Engineering | Volume 121 | Number 1 | September 1995 | Pages 67-88
Technical Paper | doi.org/10.13182/NSE121-67
Variationally Derived Coarse-Mesh Methods Based on an Alternative Flux Representation
Greg Wojtowicz, James Paul Holloway
Nuclear Science and Engineering | Volume 121 | Number 1 | September 1995 | Pages 89-102
Technical Paper | doi.org/10.13182/NSE95-A24131
Iterative Schemes for Parallel Sn Algorithms in a Shared-Memory Computing Environment
Alireza Haghighat, Melissa A. Hunter, Ronald E. Mattis
Nuclear Science and Engineering | Volume 121 | Number 1 | September 1995 | Pages 103-113
Technical Paper | doi.org/10.13182/NSE95-A24132
New Core-Reflector Boundary Conditions for Transient Nodal Reactor Calculations
Eun Ki Lee and Chang Hyo Kim and Hyung Kook Joo
Nuclear Science and Engineering | Volume 121 | Number 1 | September 1995 | Pages 114-129
Technical Paper | doi.org/10.13182/NSE95-A24133
The Green’s Function Nodal Expansion Method for Light Water Reactor Diffusion Calculations
Wei Shen, Zhongsheng Xie, Banghua Yin
Nuclear Science and Engineering | Volume 121 | Number 1 | September 1995 | Pages 130-135
Technical Paper | doi.org/10.13182/NSE95-A24134
Thermal-Spectrum Recriticality Energetics
K. N. Schwinkendorf
Nuclear Science and Engineering | Volume 121 | Number 1 | September 1995 | Pages 136-141
Technical Paper | doi.org/10.13182/NSE95-A24135
Advanced Designs and Operating Strategies to Enhance the Safety, Operability, and Efficiency of VVER-1000 Reactors
J. R. Seeker, R. W. Miller, L. T. Mayhue, R. N. Milanova
Nuclear Science and Engineering | Volume 121 | Number 1 | September 1995 | Pages 142-152
Technical Paper | doi.org/10.13182/NSE95-A24136
Void Fraction Measurements Using Neutron Radiography
Stanley S. Glickstein, William H. Vance, Hansem Joo
Nuclear Science and Engineering | Volume 121 | Number 1 | September 1995 | Pages 153-161
Technical Paper | doi.org/10.13182/NSE95-A24137
Evaluation of End-of-Cycle Moderator Temperature Coefficient Measurements for Davis-Besse Unit 1
Robert J. Borland
Nuclear Science and Engineering | Volume 121 | Number 1 | September 1995 | Pages 162-171
Technical Paper | doi.org/10.13182/NSE95-A24138
Computation of Continuous-Energy Neutron Spectra with Discrete Ordinates Transport Theory
M. L. Williams, M. Asgari
Nuclear Science and Engineering | Volume 121 | Number 2 | October 1995 | Pages 173-201
Technical Paper | doi.org/10.13182/NSE95-1
Conformal Mapping and Hexagonal Nodal Methods —I: Mathematical Foundation
Y. A. Chao, N. Tsoulfanidis
Nuclear Science and Engineering | Volume 121 | Number 2 | October 1995 | Pages 202-209
Technical Paper | doi.org/10.13182/NSE95-A28558
Conformal Mapping and Hexagonal Nodal Methods —II: Implementation in the ANC-H Code
Y. A. Chao, Y. A. Shatilla
Nuclear Science and Engineering | Volume 121 | Number 2 | October 1995 | Pages 210-225
Technical Paper | doi.org/10.13182/NSE95-A28559
Systematic Homogenization and Self-Consistent Flux and Pin Power Reconstruction for Nodal Diffusion Methods —I: Diffusion Equation-Based Theory
Hongbin Zhang, Rizwan-uddin, J. J. Dorning
Nuclear Science and Engineering | Volume 121 | Number 2 | October 1995 | Pages 226-244
Technical Paper | doi.org/10.13182/NSE95-A28560
Analytic Function Expansion Nodal Method for Hexagonal Geometry
Nam Zin Cho, Jae Man Noh
Nuclear Science and Engineering | Volume 121 | Number 2 | October 1995 | Pages 245-253
Technical Paper | doi.org/10.13182/NSE95-A28561
Comparison of PANTHER Nodal Solutions in Hexagonal-z Geometry
M. Knight, P. Hutt, I. Lewis
Nuclear Science and Engineering | Volume 121 | Number 2 | October 1995 | Pages 254-263
Technical Paper | doi.org/10.13182/NSE95-A28562
Probabilistic Method of Discrete Ordinates in a Neutron Transport Problem
V. Khromov, E. Kryuchkov, G. Tikhomirov, L. Goncharov, V. Kondakov
Nuclear Science and Engineering | Volume 121 | Number 2 | October 1995 | Pages 264-276
Technical Paper | doi.org/10.13182/NSE95-A28563
Parallel Implementation of Integral Transport Methods
Emilio Fuentes, Paul J. Turinsky
Nuclear Science and Engineering | Volume 121 | Number 2 | October 1995 | Pages 277-285
Technical Paper | doi.org/10.13182/NSE95-A28564
Calculational Verification and Process Control Applications Utilizing the High Sensitivity of Noise Measurement Parameters to Fissile System Configuration
J. T. Mihalczo, T. E. Valentine
Nuclear Science and Engineering | Volume 121 | Number 2 | October 1995 | Pages 286-300
Technical Paper | doi.org/10.13182/NSE95-A28565
Fuel-Temperature Coefficient for Boiling Water Reactor Transient Calculations: Its Dependence on Reactor Conditions
John M. Kallfelz, Lotfi A. Belblidia, Peter Grimm
Nuclear Science and Engineering | Volume 121 | Number 2 | October 1995 | Pages 301-311
Technical Paper | doi.org/10.13182/NSE95-A28566
Employing Nodal Generalized Perturbation Theory for the Minimization of Feed Enrichment During Pressurized Water Reactor In-Core Nuclear Fuel Management Optimization
G. Ivan Maldonado, Paul J. Turinsky, David J. Kropaczek,Geoffrey T. Parks
Nuclear Science and Engineering | Volume 121 | Number 2 | October 1995 | Pages 312-325
Technical Paper | doi.org/10.13182/NSE95-A28567
Qualification of the JEF2.2 Cross Sections in the Epithermal and Thermal Energy Ranges Using a Statistical Approach
Stephane Cathalau, Amal Benslimane, Abdelmajid Maghnouj, Philippe Fougeras, Vladimir Ukraintsev
Nuclear Science and Engineering | Volume 121 | Number 2 | October 1995 | Pages 326-333
Technical Paper | doi.org/10.13182/NSE95-A28568
Radiation Streaming Analysis in the Radial and Tangential Beam Tubes of a TRIGA Research Reactor Using MCNP and Comparison with Measurement
Ji Bok Lee, Byong Whie Lee, Byung Chul Lee
Nuclear Science and Engineering | Volume 121 | Number 2 | October 1995 | Pages 334-344
Technical Paper | doi.org/10.13182/NSE95-A28569
Quasi Solution of Radiation Transport Equation
Leonid R. Pogosbekyan, Dmitrij A. Lysov
Nuclear Science and Engineering | Volume 121 | Number 2 | October 1995 | Pages 345-351
Technical Paper | doi.org/10.13182/NSE95-A28570
Variational Estimates of Point-Kinetics Parameters
J. A. Favorite, W. M. Stacey, Jr.
Nuclear Science and Engineering | Volume 121 | Number 3 | December 1995 | Pages 353-370
Technical Paper | doi.org/10.13182/NSE95-A24140
Variational Derivation of Multigroup P2 Equations and Boundary Conditions in Planar Geometry
Robert P. Rulko
Nuclear Science and Engineering | Volume 121 | Number 3 | December 1995 | Pages 371-392
Technical Paper | doi.org/10.13182/NSE95-A24141
Variational P1 Approximations of General-Geometry Multigroup Transport Problems
Robert P. Rulko, Djordje Tomašević, Edward W. Larsen
Nuclear Science and Engineering | Volume 121 | Number 3 | December 1995 | Pages 393-404
Technical Paper | doi.org/10.13182/NSE121-393
An Augmented Source Method for the Application of Nodal Equivalence Theory
C. J. Hah, T. J. Downar
Nuclear Science and Engineering | Volume 121 | Number 3 | December 1995 | Pages 405-415
Technical Paper | doi.org/10.13182/NSE95-A24143
Response Matrix Properties and Convergence Implications for an Interface-Current Nodal Formulation
W. S. Yang
Nuclear Science and Engineering | Volume 121 | Number 3 | December 1995 | Pages 416-432
Technical Paper | doi.org/10.13182/NSE95-A24144
Neutron Fluence at the Pressure Vessel of a Pressurized Water Reactor Determined by the MCNP Code
Peter G. Laky, Nicholas Tsoulfanidis
Nuclear Science and Engineering | Volume 121 | Number 3 | December 1995 | Pages 433-447
Technical Paper | doi.org/10.13182/NSE95-A24145
Physics Characteristics of a Large, Passive, Pressure Tube Light Water Reactor with Voided Calandria
Pavel Hejzlar, Michael J. Driscoll, Neil E. Todreas
Nuclear Science and Engineering | Volume 121 | Number 3 | December 1995 | Pages 448-460
Technical Paper | doi.org/10.13182/NSE95-A24146
On the Compartmental Modeling of Cesium Migration in Soils
M. Antonopoulos-Domis, A. Clouvas, M. Marseguerra
Nuclear Science and Engineering | Volume 121 | Number 3 | December 1995 | Pages 461-467
Technical Paper | doi.org/10.13182/NSE95-A24147
Modeling Water Chemistry, Electrochemical Corrosion Potential, and Crack Growth Rate in the Boiling Water Reactor Heat Transport Circuits—I: The DAMAGE-PREDICTOR Algorithm
Tsung-Kuang Yeh, Digby D. Macdonald, Arthur T. Motta
Nuclear Science and Engineering | Volume 121 | Number 3 | December 1995 | Pages 468-482
Technical Paper | doi.org/10.13182/NSE95-A24148
Correlations of the Independent Fission Product Yields of Different Isotopes
Yigal Ronen
Nuclear Science and Engineering | Volume 121 | Number 3 | December 1995 | Pages 483-491
Technical Paper | doi.org/10.13182/NSE95-A24149
