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Division Spotlight
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
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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
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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Reaction Cross Sections on Carbon for Neutron Energies from 11.5 to 19 MeV
B. Antolković, G. Dietze, H. Klein
Nuclear Science and Engineering | Volume 107 | Number 1 | January 1991 | Pages 1-21
Technical Paper | doi.org/10.13182/NSE91-A23777
Determination of Neutron-Induced Alpha-Particle Cross Sections on Carbon Using the Response of a Liquid Scintillation Detector
H. J. Brede, G. Dietze, H. Klein, H. Schölermann
Nuclear Science and Engineering | Volume 107 | Number 1 | January 1991 | Pages 22-34
Technical Paper | doi.org/10.13182/NSE91-A23778
252Cf-Source-Driven Noise Measurements of Subcriticality for a Slab Tank of Aqueous Pu-U Nitrate
J. T. Mihalczo, E. D. Blakeman, G. E. Ragan, R. C. Kryter, H. Seino, R. C. Robinson
Nuclear Science and Engineering | Volume 107 | Number 1 | January 1991 | Pages 35-57
Technical Paper | doi.org/10.13182/NSE91-A23779
Comparison of Vectorization Methods Used in a Monte Carlo Code
Masayuki Nakagawa, Takamasa Mori, Makoto Sasaki
Nuclear Science and Engineering | Volume 107 | Number 1 | January 1991 | Pages 58-66
Technical Paper | doi.org/10.13182/NSE91-A23780
Study of Slab Transmission and Reflection
C. M. Eisenhauer
Nuclear Science and Engineering | Volume 107 | Number 1 | January 1991 | Pages 67-81
Technical Paper | doi.org/10.13182/NSE91-A23781
Physics of the Conceptual Design of Intense Steady Neutron Sources
Felix C. Difilippo
Nuclear Science and Engineering | Volume 107 | Number 1 | January 1991 | Pages 82-98
Technical Note | doi.org/10.13182/NSE91-A23782
Preparation, Conduct, and Experimental Results of the AVR Loss-of-Coolant Accident Simulation Test
K. Krüger, A. Bergerfurth, S. Burger, P. Pohl, M. Wimmers, J. C. Cleveland
Nuclear Science and Engineering | Volume 107 | Number 2 | February 1991 | Pages 99-113
Technical Paper | doi.org/10.13182/NSE91-A15725
Monte Carlo Calculation of Delayed Gamma Dose Rate in Complex Geometry Using the Concept of Effective Delayed Gamma Production Cross Section
S. L. Liew, L. P. Ku
Nuclear Science and Engineering | Volume 107 | Number 2 | February 1991 | Pages 114-130
Technical Paper | doi.org/10.13182/NSE91-A15726
Use of Qualitative and Quantitative Models in the Supervision of Power Plant Operations
Alex Galperin, Jean-Michel Evrard
Nuclear Science and Engineering | Volume 107 | Number 2 | February 1991 | Pages 131-141
Technical Paper | doi.org/10.13182/NSE91-A15727
KNOWBOT: An Adaptive Data Base Interface
A. Sharif Heger, Billy V. Koen
Nuclear Science and Engineering | Volume 107 | Number 2 | February 1991 | Pages 142-157
Technical Paper | doi.org/10.13182/NSE91-A15728
Adaptive Predictive Control of a Boiling Water Reactor
Chaung Lin, Shyurng-Rern Chang
Nuclear Science and Engineering | Volume 107 | Number 2 | February 1991 | Pages 158-172
Technical Paper | doi.org/10.13182/NSE91-A15729
A Mechanism for Out-of-Phase Power Instabilities in Boiling Water Reactors
José March-Leuba, E. D. Blakeman
Nuclear Science and Engineering | Volume 107 | Number 2 | February 1991 | Pages 173-179
Technical Note | doi.org/10.13182/NSE91-A15730
Monte Carlo Analysis of a Neutron Streaming Experiment
S. N. Cramer, T. Y. Lee
Nuclear Science and Engineering | Volume 107 | Number 2 | February 1991 | Pages 180-187
Technical Note | doi.org/10.13182/NSE91-A15731
A Model for Neutron Scattering Off Heavy Isotopes That Accounts for Thermal Agitation Effects
Mohamed Ouisloumen, Richard Sanchez
Nuclear Science and Engineering | Volume 107 | Number 3 | March 1991 | Pages 189-200
Technical Paper | doi.org/10.13182/NSE89-186
An Integral Sn Method for Large-Memory Supercomputers
S. P. Monahan, W. L. Filippone
Nuclear Science and Engineering | Volume 107 | Number 3 | March 1991 | Pages 201-216
Technical Paper | doi.org/10.13182/NSE91-A23785
Synthetic Acceleration Methods for Linear Transport Problems with Highly Anisotropic Scattering
Kassem M. Khattab, Edward W. Larsen
Nuclear Science and Engineering | Volume 107 | Number 3 | March 1991 | Pages 217-227
Technical Paper | doi.org/10.13182/NSE91-A23786
The Integral Line-Beam Method for Gamma Skyshine Analysis
J. Kenneth Shultis, R. E. Faw, M. S. Bassett
Nuclear Science and Engineering | Volume 107 | Number 3 | March 1991 | Pages 228-245
Technical Paper | doi.org/10.13182/NSE91-A23787
Space-Dependent Core/Reflector Boundary Conditions Generated by the Boundary Element Method for Pressurized Water Reactors
Masafumi Itagaki, Carlos A. Brebbia
Nuclear Science and Engineering | Volume 107 | Number 3 | March 1991 | Pages 246-264
Technical Paper | doi.org/10.13182/NSE91-A23788
Benchmark Calculations for the Doppler Coefficient of Reactivity
Russell D. Mosteller, Laurence D. Eisenhart, Robert C. Little, Walter J. Eich, Jason Chao
Nuclear Science and Engineering | Volume 107 | Number 3 | March 1991 | Pages 265-271
Technical Paper | doi.org/10.13182/NSE91-A23789
The Weighting Function of a Neutron Capture Detection System
F. Corvi, G. Fioni, F. Gasperini, P. B. Smith
Nuclear Science and Engineering | Volume 107 | Number 3 | March 1991 | Pages 272-283
Technical Paper | doi.org/10.13182/NSE91-A23790
Dynamic Character of Failure State in Damage Accumulation Processes
Dov Ingman, Leib Reznik
Nuclear Science and Engineering | Volume 107 | Number 3 | March 1991 | Pages 284-290
Technical Paper | doi.org/10.13182/NSE91-A23791
Reactor Diagnostics Rule Generation Through Statistical Pattern Recognition
Jaques Reifman, John C. Lee
Nuclear Science and Engineering | Volume 107 | Number 4 | April 1991 | Pages 291-314
Technical Paper | doi.org/10.13182/NSE91-A23793
Transport and Release of Radioactive Fission Products in Nuclear Fuels: The New Analytical Method of the MITRA Code
M. Gardani, C. Ronchi
Nuclear Science and Engineering | Volume 107 | Number 4 | April 1991 | Pages 315-329
Technical Paper | doi.org/10.13182/NSE91-A23794
An Angular Multigrid Acceleration Technique for Sn Equations with Highly Forward-Peaked Scattering
J. E. Morel, T. A. Manteuffel
Nuclear Science and Engineering | Volume 107 | Number 4 | April 1991 | Pages 330-342
Technical Paper | doi.org/10.13182/NSE91-A23795
One-Speed Neutron Transport Eigenvalues for Reflected Slabs and Spheres
Ninos S. Garis
Nuclear Science and Engineering | Volume 107 | Number 4 | April 1991 | Pages 343-358
Technical Paper | doi.org/10.13182/NSE91-A23796
Optimization of Linear Monte Carlo Calculations
Eugene S. Troubetzkoy
Nuclear Science and Engineering | Volume 107 | Number 4 | April 1991 | Pages 359-364
Technical Paper | doi.org/10.13182/NSE91-A23797
Cross Sections and Spectra for the 54Fe and 56Fe (n,xp) and (n,xα) Reactions Between 8 and 15 MeV
S. K. Saraf, C. E. Brient, P. M. Egun, S. M. Grimes, V. Mishra, R. S. Pedroni
Nuclear Science and Engineering | Volume 107 | Number 4 | April 1991 | Pages 365-373
Technical Paper | doi.org/10.13182/NSE88-120
Self-Powered Detector Response to Thermal and Epithermal Neutron Flux
M. N. Agu, H. Petitcolas
Nuclear Science and Engineering | Volume 107 | Number 4 | April 1991 | Pages 374-384
Technical Paper | doi.org/10.13182/NSE91-A23799
Gamma-Ray Attenuation in the Vicinity of the K Edge in Molybdenum, Tin, Lanthanum, Gadolinium, Tungsten, Lead, and Uranium
Yoshiko Harima, D. K. Trubey, Y. Sakamoto, S. Tanaka
Nuclear Science and Engineering | Volume 107 | Number 4 | April 1991 | Pages 385-393
Technical Paper | doi.org/10.13182/NSE91-A23800
A Problem in the Teaching of Reactor Kinetics
Lawrence Ruby
Nuclear Science and Engineering | Volume 107 | Number 4 | April 1991 | Pages 394-396
Technical Note | doi.org/10.13182/NSE91-A23801
