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
Aerospace Nuclear Science & Technology
Organized to promote the advancement of knowledge in the use of nuclear science and technologies in the aerospace application. Specialized nuclear-based technologies and applications are needed to advance the state-of-the-art in aerospace design, engineering and operations to explore planetary bodies in our solar system and beyond, plus enhance the safety of air travel, especially high speed air travel. Areas of interest will include but are not limited to the creation of nuclear-based power and propulsion systems, multifunctional materials to protect humans and electronic components from atmospheric, space, and nuclear power system radiation, human factor strategies for the safety and reliable operation of nuclear power and propulsion plants by non-specialized personnel and more.
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!
Latest Magazine Issues
Jan 2025
Jul 2024
Latest Journal Issues
Nuclear Science and Engineering
February 2025
Nuclear Technology
January 2025
Fusion Science and Technology
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.”
Jump to:
Comments on the Formulation of the One-Dimensional Six-Equation Two-Phase Flow Model
G. Le Coq, J. Lewi, P. Raymond
Nuclear Science and Engineering | Volume 81 | Number 1 | May 1982 | Pages 1-8
Technical Paper | doi.org/10.13182/NSE82-A19590
Code Assessment by a Two-Phase Nozzle Flow Experiment
Frank Kedziur
Nuclear Science and Engineering | Volume 81 | Number 1 | May 1982 | Pages 9-22
Technical Paper | doi.org/10.13182/NSE82-A19591
Uncertainty Analysis of Time-Dependent Nonlinear Systems: Theory and Application to Transient Thermal Hydraulics
J. Barhen, D. G. Cacuci, J. J. Wagschal, M. A. Bjerke, C. B. Mullins
Nuclear Science and Engineering | Volume 81 | Number 1 | May 1982 | Pages 23-44
Technical Paper | doi.org/10.13182/NSE82-3
On the Energy and Momentum Deposition in the Ion Beam-Pellet Interaction
S. Cuperman, B. Levush
Nuclear Science and Engineering | Volume 81 | Number 1 | May 1982 | Pages 45-54
Technical Paper | doi.org/10.13182/NSE82-A19593
Sensitivity of Computed Uranium-238 Self-Shielding Factors to the Choice of the Unresolved Average Resonance Parameters
J. L. Munoz-Cobos, G. de Saussure, R. B. Perez
Nuclear Science and Engineering | Volume 81 | Number 1 | May 1982 | Pages 55-65
Technical Paper | doi.org/10.13182/NSE82-A19594
A Modified Wigner Rational Approximation for Neutron Collision Escape Probability from Bare Homogeneous Reactor Assemblies
Anil Kumar
Nuclear Science and Engineering | Volume 81 | Number 1 | May 1982 | Pages 66-74
Technical Paper | doi.org/10.13182/NSE82-A19595
Conserving Average Rate of Energy Loss in Transport Calculations for Light Charged Particles
D. E. Cullen, S. T. Perkins
Nuclear Science and Engineering | Volume 81 | Number 1 | May 1982 | Pages 75-91
Technical Paper | doi.org/10.13182/NSE82-A19596
Numerical Analysis of the Boltzmann Equation Including Fokker-Planck Terms
K. Przybylski, J. Ligou
Nuclear Science and Engineering | Volume 81 | Number 1 | May 1982 | Pages 92-109
Technical Paper | doi.org/10.13182/NSE82-A19597
Asymptotic Equivalence of Neutron Diffusion and Transport in Time-Independent Reactor Systems
Mieczysłew Borysiewicz, Janusz Mika, Giampiero Spiga
Nuclear Science and Engineering | Volume 81 | Number 1 | May 1982 | Pages 110-118
Technical Paper | doi.org/10.13182/NSE82-A19598
Binary Operators and Their Green's Functions
James R. Sheff
Nuclear Science and Engineering | Volume 81 | Number 1 | May 1982 | Pages 119-136
Technical Paper | doi.org/10.13182/NSE82-A19599
Neutron Diffusion in Graphite Poisoned with 1/v and Non-1/v Absorbers
U. Malik, L. S. Kothari, A. Kumar
Nuclear Science and Engineering | Volume 81 | Number 1 | May 1982 | Pages 137-143
Technical Note | doi.org/10.13182/NSE82-A19600
An Equivalence Relation for a Doubly Heterogenous Lattice
M. Segev
Nuclear Science and Engineering | Volume 81 | Number 2 | June 1982 | Pages 151-160
Technical Paper | doi.org/10.13182/NSE82-A20082
Measurements of Neutron and Gamma-Ray Streaming in a Cavity-Duct System and an Analysis by an Albedo Monte Carlo Method
Kazuo Shin, Ryuji Murakami, Hiroaki Taniuchi, Tomonori Hyodo, Yoshiaki Oka
Nuclear Science and Engineering | Volume 81 | Number 2 | June 1982 | Pages 161-171
Technical Paper | doi.org/10.13182/NSE82-A20083
Effect of Fluorescence, Bremsstrahlung, and Annihilation Radiation on the Spectra and Energy Deposition of Gamma Rays in Bulk Media
K. V. Subbaiah, A. Natarajan, D. V. Gopinath, D. K. Trubey
Nuclear Science and Engineering | Volume 81 | Number 2 | June 1982 | Pages 172-195
Technical Paper | doi.org/10.13182/NSE82-A20084
Absolute Measurement of the Uranium-235 Fission Cross Section from 0.2 to 1.2 MeV
Oren A. Wasson, Michael M. Meier, Kenneth C. Duvall
Nuclear Science and Engineering | Volume 81 | Number 2 | June 1982 | Pages 196-212
Technical Paper | doi.org/10.13182/NSE82-A20085
New Calculation of Prompt Fission Neutron Spectra and Average Prompt Neutron Multiplicities
David G. Madland, J. Rayford Nix
Nuclear Science and Engineering | Volume 81 | Number 2 | June 1982 | Pages 213-271
Technical Paper | doi.org/10.13182/NSE82-5
An Extension of the Nodal Green's Function Method for Reactor Analysis
Chang Yu-Man, L. M. Grossman, P. L. Chambré, B. S. Lew
Nuclear Science and Engineering | Volume 81 | Number 2 | June 1982 | Pages 272-280
Technical Note | doi.org/10.13182/NSE82-A20087
Statistical Screening of Input Variables in a Complex Computer Code
Theodore J. Krieger
Nuclear Science and Engineering | Volume 81 | Number 2 | June 1982 | Pages 281-283
Technical Note | doi.org/10.13182/NSE82-A20088
Derivation of a Dose Mean Value of Lineal Energy from Variance Measurements of a Secondary Electron Emission Current
B. Forsberg
Nuclear Science and Engineering | Volume 81 | Number 2 | June 1982 | Pages 283-290
Technical Note | doi.org/10.13182/NSE82-A20089
KINE—A One-Dimensional Dynamics Program for Pressurized Water Reactors with Partial Boiling in the Core
R. Fiebig, A. Krüger
Nuclear Science and Engineering | Volume 81 | Number 2 | June 1982 | Pages 291-298
Technical Note | doi.org/10.13182/NSE82-A20090
A Note on Estimation of Pressure Sensor Time Constant from the Normal Operating Data
S. M. Wu, M. S. Ouyang
Nuclear Science and Engineering | Volume 81 | Number 2 | June 1982 | Pages 298-299
Technical Note | doi.org/10.13182/NSE82-A20091
Interfacial Exchange Relations for Two-Fluid Vapor-Liquid Flow: A Simplified Regime-Map Approach
J. E. Kelly, M. S. Kazimi
Nuclear Science and Engineering | Volume 81 | Number 3 | July 1982 | Pages 305-318
Technical Paper | doi.org/10.13182/NSE82-A20276
Wall Heat Transfer Coefficient for Condensation and Boiling in Forced Convection of Sodium
H. C. No, M. S. Kazimi
Nuclear Science and Engineering | Volume 81 | Number 3 | July 1982 | Pages 319-324
Technical Paper | doi.org/10.13182/NSE82-A20277
Neutron and Gamma-Ray Doses at Hiroshima and Nagasaki
W. E. Loewe, E. Mendelsohn
Nuclear Science and Engineering | Volume 81 | Number 3 | July 1982 | Pages 325-350
Technical Paper | doi.org/10.13182/NSE82-A20278
Subcritical Limits for Uranium-235 Systems
Hugh K. Clark
Nuclear Science and Engineering | Volume 81 | Number 3 | July 1982 | Pages 351-378
Technical Paper | doi.org/10.13182/NSE82-A20279
Subcritical Limits for Uranium-233 Systems
Nuclear Science and Engineering | Volume 81 | Number 3 | July 1982 | Pages 379-395
Technical Paper | doi.org/10.13182/NSE82-A20280
The Isomeric Ratio in Thermal and Fast Neutron Capture of Americium-241
K. Wisshak, J. Wickenhauser, F. Käppeler, G. Reffo, F. Fabbri
Nuclear Science and Engineering | Volume 81 | Number 3 | July 1982 | Pages 396-417
Technical Paper | doi.org/10.13182/NSE82-6
Cesium-133 Neutron Capture Cross Section
R. L. Macklin
Nuclear Science and Engineering | Volume 81 | Number 3 | July 1982 | Pages 418-422
Technical Paper | doi.org/10.13182/NSE82-A20282
Cross-Section Adjustment with Monte Carlo Sensitivities: Application to the Winfrith Iron Benchmark
M. C. G. Hall
Nuclear Science and Engineering | Volume 81 | Number 3 | July 1982 | Pages 423-431
Technical Paper | doi.org/10.13182/NSE82-A20283
Eigenvalue-Dependent Neutron Energy Spectra: Definitions, Analyses, and Applications
D. G. Cacuci, Y. Ronen, Z. Shayer, J. J. Wagschal, Y. Yeivin
Nuclear Science and Engineering | Volume 81 | Number 3 | July 1982 | Pages 432-442
Technical Paper | doi.org/10.13182/NSE82-A20284
Particle and Radiation Leakage Importance: Definition, Analysis, and Interpretation
D. G. Cacuci, J.J. Wagschal, A. Yaari
Nuclear Science and Engineering | Volume 81 | Number 3 | July 1982 | Pages 443-450
Technical Paper | doi.org/10.13182/NSE82-A20285
The Effects of Intracell Adjoint Flux Heterogeneity on First-Order Perturbation Reactivity Calculations
K. S. Smith
Nuclear Science and Engineering | Volume 81 | Number 3 | July 1982 | Pages 451-458
Technical Paper | doi.org/10.13182/NSE82-A20286
An Unequal Velocity, Unequal Temperature Two-Fluid Description of Transient Vapor-Liquid Flow in Channels
Ramendra P. Roy, S. Allen Ho
Nuclear Science and Engineering | Volume 81 | Number 3 | July 1982 | Pages 459-467
Technical Note | doi.org/10.13182/NSE82-A20287
STP: A Mathematically and Physically, Consistent Library of Steam, Properties
F. Aguilar, P. G. Tuttle, A. C. Hutter
Nuclear Science and Engineering | Volume 81 | Number 3 | July 1982 | Pages 467-471
Technical Note | doi.org/10.13182/NSE82-A20288
Parallel Neutron Diffusion in Plane Lattices with Voids
T. Duracz
Nuclear Science and Engineering | Volume 81 | Number 3 | July 1982 | Pages 471-472
Technical Note | doi.org/10.13182/NSE82-A20289
Neutron Diffusion in Asymmetric Cell Lattices
Nuclear Science and Engineering | Volume 81 | Number 3 | July 1982 | Pages 472-474
Technical Note | doi.org/10.13182/NSE82-A20290
On Angular Flux Computations in Neutron-Transport Theory
R. D. M. Garcia, C. E. Siewert
Nuclear Science and Engineering | Volume 81 | Number 3 | July 1982 | Pages 474-476
Technical Note | doi.org/10.13182/NSE82-A20291
Evidence for a Time-Dependent Neutron Flux/Spectrum Anomaly at the Transient Reactor Test Facility
A. H. Lumpkin, G. J. Berzins
Nuclear Science and Engineering | Volume 81 | Number 3 | July 1982 | Pages 477-481
Technical Note | doi.org/10.13182/NSE82-A20292
Neutron Scattering Cross Sections for 232Th, 233U, 235U, 238U, 239Pu, and 242PU Between 0.6 and 3.4 MeV
G. Haouat, J. Lachkar, Ch. Lagrange, J. Jary, J. Sigaud, Y. Patin
Nuclear Science and Engineering | Volume 81 | Number 4 | August 1982 | Pages 491-511
Technical Paper | doi.org/10.13182/NSE82-A21439
Measurement of the Neutron-Induced Fission Cross Section of 232Th Relative to 235U from 0.7 to 30 MeV
J. W. Behrens, J. C. Browne, E. Abies
Nuclear Science and Engineering | Volume 81 | Number 4 | August 1982 | Pages 512-519
Technical Paper | doi.org/10.13182/NSE82-A21440
Technetium-99 Neutron Capture Cross Section
Nuclear Science and Engineering | Volume 81 | Number 4 | August 1982 | Pages 520-524
Technical Paper | doi.org/10.13182/NSE82-A21441
Fast Neutron Activation of 48.6-min 111mCd in Natural Cadmium
Donald L. Smith, James W. Meadows
Nuclear Science and Engineering | Volume 81 | Number 4 | August 1982 | Pages 525-531
Technical Paper | doi.org/10.13182/NSE82-A21442
Decay of Fast Neutron Pulses in Uranium Assemblies
Rajesh Mohan, Feroz Ahmed, L. S. Kothari
Nuclear Science and Engineering | Volume 81 | Number 4 | August 1982 | Pages 532-539
Technical Paper | doi.org/10.13182/NSE82-A21443
A Model for Effective Thermal Conductivity of Unrestructured Sphere-Pac Fuel
M. J. Ades, K. L. Peddicord
Nuclear Science and Engineering | Volume 81 | Number 4 | August 1982 | Pages 540-550
Technical Paper | doi.org/10.13182/NSE82-A21444
Interference Effect of Neutron Streaming Between Different Fast Critical Assembly Cells
T. Takeda, E. Wachi
Nuclear Science and Engineering | Volume 81 | Number 4 | August 1982 | Pages 551-557
Technical Note | doi.org/10.13182/NSE82-A21445
Effect of Collective and Quantum Modifications of the Energy Deposition in the Simulation of Ion Beam-Pellet Interaction
B. Levush, S. Cuperman
Nuclear Science and Engineering | Volume 81 | Number 4 | August 1982 | Pages 557-560
Technical Note | doi.org/10.13182/NSE82-A21446
Determination of Fuel-Clad Thermal Gap Conductance by Use of Kalman Filter Methods
C.C. Meek, R. C. Doerner, W. J. Adams
Nuclear Science and Engineering | Volume 81 | Number 4 | August 1982 | Pages 560-562
Technical Note | doi.org/10.13182/NSE82-A21447
Effective Thermal Conductivity of Sphere-Pac Fuel During Restructuring
Nuclear Science and Engineering | Volume 81 | Number 4 | August 1982 | Pages 563-569
Technical Note | doi.org/10.13182/NSE82-A21448