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
Decommissioning & Environmental Sciences
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.
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!
Latest Magazine Issues
Apr 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
June 2025
Nuclear Technology
Fusion Science and Technology
May 2025
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.
Jump to:
A New Approach to the Adjustment of Group Cross Sections Fitting Integral Measurements
Yung-An Chao
Nuclear Science and Engineering | Volume 72 | Number 1 | October 1979 | Pages 1-8
Technical Paper | doi.org/10.13182/NSE79-A19304
An Application of the Transmission Probability Method to the Calculation of Neutron Flux Distributions in Hexagonal Geometry
Frej Wasastjerna
Nuclear Science and Engineering | Volume 72 | Number 1 | October 1979 | Pages 9-18
Technical Paper | doi.org/10.13182/NSE79-A19305
A Method for Data Evaluation with Lognormal Distributions
F. Schmittroth
Nuclear Science and Engineering | Volume 72 | Number 1 | October 1979 | Pages 19-34
Technical Paper | doi.org/10.13182/NSE79-A19306
Neutron and Gamma-Ray Spectra from 232Th, 235U, 238U, and 239Pu After Bombardment with 14-MeV Neutrons
Luisa F. Hansen, Calvin Wong, Ted T. Komoto, Bertram A. Pohl, Eugene Goldberg, Robert J. Howerton, Walter M. Webster
Nuclear Science and Engineering | Volume 72 | Number 1 | October 1979 | Pages 35-51
Technical Paper | doi.org/10.13182/NSE79-A19307
Measurement of the Doppler Effect in Uranium-238
Francis Y. Tsang, Robert M. Brugger
Nuclear Science and Engineering | Volume 72 | Number 1 | October 1979 | Pages 52-64
Technical Paper | doi.org/10.13182/NSE79-A19308
Neutron Spectra Determination by Resonance Reactions
Hugh F. Henry
Nuclear Science and Engineering | Volume 72 | Number 1 | October 1979 | Pages 65-74
Technical Paper | doi.org/10.13182/NSE79-A19309
Scaling Laws for Modeling Nuclear Reactor Systems
Amir N. Nahavandi, Frank S. Castellana, Edick N. Moradkhanian
Nuclear Science and Engineering | Volume 72 | Number 1 | October 1979 | Pages 75-83
Technical Paper | doi.org/10.13182/NSE79-A19310
The Determination of Time Constants of Reactor Pressure and Temperature Sensors: The Dynamic Data System Method
S. M. Wu, M. C. Hsu, M. C. Chow
Nuclear Science and Engineering | Volume 72 | Number 1 | October 1979 | Pages 84-96
Technical Paper | doi.org/10.13182/NSE79-A19311
The Sensitivity of Emergency Core Coolant Bypass and Lower Plenum Refill to Apparatus Scale Size and Lower Plenum Pressure in a Pressurized Water Reactor
Bart J. Daly
Nuclear Science and Engineering | Volume 72 | Number 1 | October 1979 | Pages 97-107
Technical Paper | doi.org/10.13182/NSE79-A19312
On the Analysis of the Variance in Monte Carlo Calculations
Arie Dubi
Nuclear Science and Engineering | Volume 72 | Number 1 | October 1979 | Pages 108-110
Technical Note | doi.org/10.13182/NSE79-A19313
Inverse Perturbation Theory
Yigal Ronen
Nuclear Science and Engineering | Volume 72 | Number 1 | October 1979 | Pages 110-113
Technical Note | doi.org/10.13182/NSE79-A19314
Cross Sections for the Reactions 54Fe(n, α)51Cr, 54Fe(n, p)54Mn, and 56Fe(n, p)56Mn
A. Paulsen, R. Widera, F. Arnotte, H. Liskien
Nuclear Science and Engineering | Volume 72 | Number 1 | October 1979 | Pages 113-116
Technical Note | doi.org/10.13182/NSE79-A19315
Iron Oxide Deposition on Heated Surfaces in Pressurized Boiling Water
Yamato Asakura, Makoto Kikuchi, Shunsuke Uchida, Hideo Yusa, Minoru Miki
Nuclear Science and Engineering | Volume 72 | Number 1 | October 1979 | Pages 117-120
Technical Note | doi.org/10.13182/NSE79-A19316
Simultaneous Freezing and Melting in Finite Media
S. J. Hakim
Nuclear Science and Engineering | Volume 72 | Number 2 | November 1979 | Pages 129-139
Technical Paper | doi.org/10.13182/NSE79-A19458
Instantaneous Fuel Growth Rates for Breeder Reactors
P. J. Maudlin, K. O. Ott, R. C. Borg
Nuclear Science and Engineering | Volume 72 | Number 2 | November 1979 | Pages 140-151
Technical Paper | doi.org/10.13182/NSE79-A19459
Description of Reactor Fuel Breeding with Three Integral Concepts
K. O. Ott, N. A. Hanan, P. J. Maudlin, R. C. Borg
Nuclear Science and Engineering | Volume 72 | Number 2 | November 1979 | Pages 152-159
Technical Paper | doi.org/10.13182/NSE79-A19460
Anisotropy in the Scattering of Thermal Neutrons in Crystalline Moderators—Beryllium
A. N. Verma, Balesh Verma, Feroz Ahmed, L. S. Kothari
Nuclear Science and Engineering | Volume 72 | Number 2 | November 1979 | Pages 160-174
Technical Paper | doi.org/10.13182/NSE79-A19461
Integral Tests of Neutron Activation Cross Sections in a 9Be(d,n) Field at Ed = 40 MeV
L. R. Greenwood, R. R. Heinrich, M. J. Saltmarsh, C. B. Fulmer
Nuclear Science and Engineering | Volume 72 | Number 2 | November 1979 | Pages 175-190
Technical Paper | doi.org/10.13182/NSE79-A19462
Gamma-Ray Production and Inferred Inelastic Neutron Cross Sections for Nickel Isotopes
S. Traiforos, A. Mittler, W. A. Schier, B. K. Barnes, L. E. Beghian, P. Harihar
Nuclear Science and Engineering | Volume 72 | Number 2 | November 1979 | Pages 191-201
Technical Paper | doi.org/10.13182/NSE79-A19463
Neutron Cross Sections of Thorium-232
R. E. Chrien, H. I. Liou, M. J. Kenny, M. L. Stelts
Nuclear Science and Engineering | Volume 72 | Number 2 | November 1979 | Pages 202-215
Technical Paper | doi.org/10.13182/NSE79-A19464
Theoretical Beta Spectrum from Uranium-235 Fission Fragments in Secular Equilibrium
F. T. Avignone III, L. P. Hopkins, Z. D. Greenwood
Nuclear Science and Engineering | Volume 72 | Number 2 | November 1979 | Pages 216-221
Technical Paper | doi.org/10.13182/NSE79-A19465
Simulated (n,f) Cross Sections for Exotic Actinide Nuclei
H. C. Britt, J. B. Wilhelmy
Nuclear Science and Engineering | Volume 72 | Number 2 | November 1979 | Pages 222-229
Technical Paper | doi.org/10.13182/NSE72-222
A Critical Assembly of Uranium Enriched to 10% in Uranium-235
G. E. Hansen, H. C. Paxton
Nuclear Science and Engineering | Volume 72 | Number 2 | November 1979 | Pages 230-236
Technical Paper | doi.org/10.13182/NSE79-A19467
Discrete Eigenvalues of the Neutron Transport Equation with Anisotropic Scattering
Trine-Yie Dawn, Ing-Jane Chen
Nuclear Science and Engineering | Volume 72 | Number 2 | November 1979 | Pages 237-243
Technical Paper | doi.org/10.13182/NSE72-237
The Derivation of Neutron Generation Time for Reflected Systems and Its Physical Interpretation
Yoshihiro Yamane, Minoru Shinkawa, Kojiro Nishina
Nuclear Science and Engineering | Volume 72 | Number 2 | November 1979 | Pages 244-255
Technical Paper | doi.org/10.13182/NSE79-A19469
Asymptotic Stability of Coupled-Core Reactors with Arbitrary Reactivity Feedback and No Coupling Time Lag
M. Podowski
Nuclear Science and Engineering | Volume 72 | Number 2 | November 1979 | Pages 256-261
Technical Paper | doi.org/10.13182/NSE79-A19470
Measurement of the Energy Spectrum of a Fast Electron Beam
Chiaki Yamamoto
Nuclear Science and Engineering | Volume 72 | Number 2 | November 1979 | Pages 262-265
Technical Note | doi.org/10.13182/NSE79-A19471
A Method for Solving the Xenon Oscillation Control Problem
Walter Hanke
Nuclear Science and Engineering | Volume 72 | Number 2 | November 1979 | Pages 265-272
Technical Note | doi.org/10.13182/NSE79-A19472
Criticality of Neptunium-237 and Its Possible Utilization in Nuclear Reactors
W. Seifritz, P. Wydler
Nuclear Science and Engineering | Volume 72 | Number 2 | November 1979 | Pages 272-276
Technical Note | doi.org/10.13182/NSE79-A19473
Maximum Density and Capture Rate of Neutrons Moderated from a Pulsed Source
G. C. Baldwin, J. C. Solem
Nuclear Science and Engineering | Volume 72 | Number 3 | December 1979 | Pages 281-289
Technical Paper | doi.org/10.13182/NSE79-A20384
The Direct Pumping of Gamma-Ray Lasers by Neutron Capture
Nuclear Science and Engineering | Volume 72 | Number 3 | December 1979 | Pages 290-292
Technical Paper | doi.org/10.13182/NSE79-A20385
The Interaction of Fast Neutrons with Nickel-60
A. Smith, P. Guenther, D. Smith, J. Whalen
Nuclear Science and Engineering | Volume 72 | Number 3 | December 1979 | Pages 293-303
Technical Paper | doi.org/10.13182/NSE79-A20386
Linear Response of the Neutron Field to a Propagating Perturbation of Moderator Density (Two-Group Theory of Boiling Water Reactor Noise)
K. Behringer, G. Kosály, I. Pázsit
Nuclear Science and Engineering | Volume 72 | Number 3 | December 1979 | Pages 304-321
Technical Paper | doi.org/10.13182/NSE79-A20387
One-Dimensional Network for Multidimensional Fluid-Structural Interactions
K. Takeuchi
Nuclear Science and Engineering | Volume 72 | Number 3 | December 1979 | Pages 322-329
Technical Paper | doi.org/10.13182/NSE79-A20388
Dissociating Nitrogen Tetroxide (N2O4) as a Working Fluid in Thermodynamic Cycles
Alecsei Sorokin
Nuclear Science and Engineering | Volume 72 | Number 3 | December 1979 | Pages 330-346
Technical Paper | doi.org/10.13182/NSE79-A20389
The Initiation of Melt Fragmentation in Fuel-Coolant Interactions
Douglas S. Drumheller
Nuclear Science and Engineering | Volume 72 | Number 3 | December 1979 | Pages 347-356
Technical Paper | doi.org/10.13182/NSE79-A20390
The Thermal-Neutron Capture Cross Section for the Production of 108mAg
T. B. Ryves
Nuclear Science and Engineering | Volume 72 | Number 3 | December 1979 | Pages 357-359
Technical Note | doi.org/10.13182/NSE79-A20391
The Th(n,xγ) Reaction Cross Section for Neutrons of Energy Between 0.3 and 20 MeV
G. L. Morgan
Nuclear Science and Engineering | Volume 72 | Number 3 | December 1979 | Pages 359-361
Technical Note | doi.org/10.13182/NSE79-A20392
Improved Treatment of the Neutron Streaming Through Control Rod Followers in a Sodium-Cooled Fast Reactor
Tadashi Yoshida
Nuclear Science and Engineering | Volume 72 | Number 3 | December 1979 | Pages 361-365
Technical Note | doi.org/10.13182/NSE79-A20393