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The Young Members Group works to encourage and enable all young professional members to be actively involved in the efforts and endeavors of the Society at all levels (Professional Divisions, ANS Governance, Local Sections, etc.) as they transition from the role of a student to the role of a professional. It sponsors non-technical workshops and meetings that provide professional development and networking opportunities for young professionals, collaborates with other Divisions and Groups in developing technical and non-technical content for topical and national meetings, encourages its members to participate in the activities of the Groups and Divisions that are closely related to their professional interests as well as in their local sections, introduces young members to the rules and governance structure of the Society, and nominates young professionals for awards and leadership opportunities available to members.
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November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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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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This year, the U.S. nuclear industry received a much-needed economic boost that could help preserve operating nuclear power plants and incentivize upgrades that extend their lifespan and power output.
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Accuracy of Coarse Group Calculations in Fast Reactors
D. Antonakas, R. Corcuera, P. Govaerts
Nuclear Science and Engineering | Volume 48 | Number 1 | May 1972 | Pages 1-9
Technical Paper | doi.org/10.13182/NSE72-A22451
A Generalized Model for the Elastic and Inelastic Slowing Down of Fast Neutrons
B. Rocca-Volmerange
Nuclear Science and Engineering | Volume 48 | Number 1 | May 1972 | Pages 10-15
Technical Paper | doi.org/10.13182/NSE72-A22452
Synthesis of Three-Dimensional Transport Problems Using Two-Dimensional Trial Functions
M. Natelson
Nuclear Science and Engineering | Volume 48 | Number 1 | May 1972 | Pages 16-27
Technical Paper | doi.org/10.13182/NSE72-A22453
Explosive Disassembly of Fast Reactors
John C. Lee, Thomas H. Pigford
Nuclear Science and Engineering | Volume 48 | Number 1 | May 1972 | Pages 28-44
Technical Paper | doi.org/10.13182/NSE72-A22454
Measurement and Analysis of Neutron Spectra in a Fast Subcritical Assembly Containing Uranium-235, Uranium-238, and Beryllium Oxide
J. C. Young, J. M. Neill, P. d’Oultremont, E.L. Slaggie, C. A. Preskitt
Nuclear Science and Engineering | Volume 48 | Number 1 | May 1972 | Pages 45-50
Technical Paper | doi.org/10.13182/NSE72-A22455
The Spectral Distribution of Neutrons and Neutron Reaction Cross Sections in an Unreflected Uranium-235 Critical Assembly and the Fission Neutron Spectrum
W. N. McElroy, R. J. Armani, E. Tochilin
Nuclear Science and Engineering | Volume 48 | Number 1 | May 1972 | Pages 51-71
Technical Paper | doi.org/10.13182/NSE72-A22456
On the Energy Loss of Fission Fragments in Composite Systems
M. Hakim, N. H. Shafrir
Nuclear Science and Engineering | Volume 48 | Number 1 | May 1972 | Pages 72-77
Technical Paper | doi.org/10.13182/NSE72-A22457
The Neutron Induced Gamma-Ray Reactions in Calcium in the Energy Range 4.85≤ En ≤8.05 MeV
J. K. Dickens
Nuclear Science and Engineering | Volume 48 | Number 1 | May 1972 | Pages 78-86
Technical Paper | doi.org/10.13182/NSE72-A22458
Periodicity in Annular Diffuser Flow
F. R. Fricke
Nuclear Science and Engineering | Volume 48 | Number 1 | May 1972 | Pages 87-102
Technical Paper | doi.org/10.13182/NSE72-A22459
Theoretical Heat Transfer Predictions for Finite Nuclear Fuel Rod Assemblies
T. Ginsberg, D. M. France
Nuclear Science and Engineering | Volume 48 | Number 1 | May 1972 | Pages 103-114
Technical Paper | doi.org/10.13182/NSE72-A22460
Extension of Linearly Anisotropic Asymptotic Neutron Diffusion Theory to Reflected Systems
B. L. Koponen, R. J. Doyas
Nuclear Science and Engineering | Volume 48 | Number 1 | May 1972 | Pages 115-118
Technical Paper | doi.org/10.13182/NSE72-A22461
On the Scattering Matrix Construction for the Discrete Energy Representation of Thermal-Neutron Spectra
M. V. Mataušek
Nuclear Science and Engineering | Volume 48 | Number 1 | May 1972 | Pages 119-120
Technical Paper | doi.org/10.13182/NSE72-A22462
Linearization of Sparrow and Koopman’s Method for Heat Transfer with Variable Conductivity
Marc Dixmier
Nuclear Science and Engineering | Volume 48 | Number 1 | May 1972 | Pages 121-122
Technical Paper | doi.org/10.13182/NSE72-A22463
Measurement of the Local Void Fraction at High Pressure in a Heating Channel
Robert Martin
Nuclear Science and Engineering | Volume 48 | Number 2 | June 1972 | Pages 125-138
Technical Paper | doi.org/10.13182/NSE72-A22466
Thermal, Radiation, and Mechanical Analysis for Unsteady-State Fuel Restructuring of Cylindrical Oxide Elements in Fast Reactors
C. K. Cheng, B. M. Ma
Nuclear Science and Engineering | Volume 48 | Number 2 | June 1972 | Pages 139-158
Technical Paper | doi.org/10.13182/NSE72-A22467
Low-Energy Electron Transport by the Method of Discrete Ordinates
D. E. Bartine, R. G. Alsmiller, Jr., F. R. Mynatt, W. W. Engle, Jr., J. Barish
Nuclear Science and Engineering | Volume 48 | Number 2 | June 1972 | Pages 159-178
Technical Paper | doi.org/10.13182/NSE72-A22468
The Adjoint Difference Method and Its Application to Deep-Penetration Radiation Transport
T. J. Hoffman, J. C. Robinson, P. N. Stevens
Nuclear Science and Engineering | Volume 48 | Number 2 | June 1972 | Pages 179-188
Technical Paper | doi.org/10.13182/NSE72-A22469
The Shielding Factor Method of Generating Multigroup Cross Sections for Fast Reactor Analysis
R. B. Kidman, R. E. Schenter, R. W. Hardie, W. W. Little
Nuclear Science and Engineering | Volume 48 | Number 2 | June 1972 | Pages 189-201
Technical Paper | doi.org/10.13182/NSE72-A22470
Reactor Parameters from Neutron and Gamma-Ray Noise Measurements
Bruno Bärs, Esko Markkanen
Nuclear Science and Engineering | Volume 48 | Number 2 | June 1972 | Pages 202-210
Technical Paper | doi.org/10.13182/NSE72-A22471
Solution Bounds for Nonlinear Space-Time Reactor Problems
David B. Reister, Paul L. Chambré
Nuclear Science and Engineering | Volume 48 | Number 2 | June 1972 | Pages 211-218
Technical Paper | doi.org/10.13182/NSE72-A22472
Values of the Neutron Resonance Capture Integral for Some Rare Earth Isotopes
F. Rahn, H. S. Camarda, G. Hacken, W. W. Havens, Jr., H. I. Liou, J. Rainwater, M. Slagowitz, S. Wynchank
Nuclear Science and Engineering | Volume 48 | Number 2 | June 1972 | Pages 219-221
Technical Note | doi.org/10.13182/NSE72-A22474
Optimization of Importance-Sampling Parameters in Monte Carlo
D. B. MacMillan
Nuclear Science and Engineering | Volume 48 | Number 2 | June 1972 | Page 219
Technical Note | doi.org/10.13182/NSE72-A22473
The Total Neutron Cross Section of Lithium-6 from 100 to 1500 keV
J. W. Meadows, J. F. Whalen
Nuclear Science and Engineering | Volume 48 | Number 2 | June 1972 | Pages 221-224
Technical Note | doi.org/10.13182/NSE72-A22475
A Note on the Existence of a Minimum Value for the Neutron Diffusion Length
O. I. Öztunali, A. I. Usseli
Nuclear Science and Engineering | Volume 48 | Number 2 | June 1972 | Pages 224-225
Technical Note | doi.org/10.13182/NSE72-A22476
Motion Induced Shifts in Neutron Resonance Absorptions
R. M. Ball, T. G. Williamson
Nuclear Science and Engineering | Volume 48 | Number 2 | June 1972 | Pages 225-227
Technical Note | doi.org/10.13182/NSE72-A22477
On the Effective Booster Rod
Tohru Haga
Nuclear Science and Engineering | Volume 48 | Number 2 | June 1972 | Pages 227-231
Technical Note | doi.org/10.13182/NSE72-A22478
Nodal Equations Derived from Invariant Imbedding Theory
Zbigniew Weiss
Nuclear Science and Engineering | Volume 48 | Number 3 | July 1972 | Pages 235-247
Technical Paper | doi.org/10.13182/NSE72-A22482
Temperature-Dependent Intermediate Neutron Resonance Integrals
Rubin Goldstein
Nuclear Science and Engineering | Volume 48 | Number 3 | July 1972 | Pages 248-254
Technical Paper | doi.org/10.13182/NSE72-A22483
A Critical Time Step Approach to Monte Carlo Reliability Calculation
G. C. Geisler, R. E. Zindler
Nuclear Science and Engineering | Volume 48 | Number 3 | July 1972 | Pages 255-265
Technical Paper | doi.org/10.13182/NSE72-A22484
Monte Carlo Evaluation of Multiple Scattering and Resolution Effects in Double-Differential Neutron Scattering Cross-Section Measurements
F. G. Bischoff, M. L. Yeater, W. E. Moore
Nuclear Science and Engineering | Volume 48 | Number 3 | July 1972 | Pages 266-280
Technical Paper | doi.org/10.13182/NSE48-266
The Double Filter Technique for the Investigation of Thermal-Neutron Spectra
D. Antonini, E. Omicini, F. Pistella
Nuclear Science and Engineering | Volume 48 | Number 3 | July 1972 | Pages 281-299
Technical Paper | doi.org/10.13182/NSE72-A22486
Criticality of Plutonium Nitrate Solution Containing Soluble Gadolinium
R. C. Lloyd, E. D. Clayton, L. E. Hansen
Nuclear Science and Engineering | Volume 48 | Number 3 | July 1972 | Pages 300-304
Technical Paper | doi.org/10.13182/NSE72-A22487
Oscillation of Fissile Materials in Thermal-Neutron Critical Assemblies: The Equivalent Sample Method
B. Laponche, M. Brunet, Y. Bouedo
Nuclear Science and Engineering | Volume 48 | Number 3 | July 1972 | Pages 305-318
Technical Paper | doi.org/10.13182/NSE72-A22488
Half-Lives of Radionuclides—IV
J. F. Emery, S. A. Reynolds, E. I. Wyatt, G. I. Gleason
Nuclear Science and Engineering | Volume 48 | Number 3 | July 1972 | Pages 319-323
Technical Paper | doi.org/10.13182/NSE72-A22489
A Measurement of the Capture-to-Fission Cross Section Ratios of Uranium-235 and Plutonium-239 with a New Technique
R. E. Bandl, H. Miessner, F. H. Fröhner
Nuclear Science and Engineering | Volume 48 | Number 3 | July 1972 | Pages 324-330
Technical Paper | doi.org/10.13182/NSE72-A22490
Calculational Model for Self-Powered Neutron Detector
H. D. Warren
Nuclear Science and Engineering | Volume 48 | Number 3 | July 1972 | Pages 331-342
Technical Paper | doi.org/10.13182/NSE72-A22491
Electromagnetic Pulse and Time-Dependent Escape of Neutrons and Gamma Rays from a Nuclear Explosion
H. A. Sandmeier, S. A. Dupree, G. E. Hansen
Nuclear Science and Engineering | Volume 48 | Number 3 | July 1972 | Pages 343-352
Technical Paper | doi.org/10.13182/NSE72-A22492
Analytical Determination of Freeze-Seal Stem Length for Sodium Components
S. M. Cho
Nuclear Science and Engineering | Volume 48 | Number 3 | July 1972 | Pages 353-358
Technical Paper | doi.org/10.13182/NSE72-A22493
Marshak Conditions Applicable in Spherical Geometry to the Simplified Spherical Harmonics Equations
Alan Staub, E. M. Gelbard
Nuclear Science and Engineering | Volume 48 | Number 3 | July 1972 | Pages 359-361
Technical Note | doi.org/10.13182/NSE72-A22494
Time-Dependent Phenomena in Neutron Slowing Down Theory
Robert Conn, Mohamed Sawan
Nuclear Science and Engineering | Volume 48 | Number 3 | July 1972 | Pages 361-366
Technical Note | doi.org/10.13182/NSE72-A22495
Critical Assemblies and Reactor Research
Aubrey F. Thomas
Nuclear Science and Engineering | Volume 48 | Number 3 | July 1972 | Page 367
Technical Note | doi.org/10.13182/NSE72-A22496
Radioisotope Instruments, Part 1
Louis Costrell
Nuclear Science and Engineering | Volume 48 | Number 3 | July 1972 | Pages 367-368
Technical Note | doi.org/10.13182/NSE72-A22497
Annual Review of Nuclear Science
Lothar W. Nordheim
Nuclear Science and Engineering | Volume 48 | Number 3 | July 1972 | Pages 368-369
Technical Note | doi.org/10.13182/NSE72-A22498
Comment on a p-Wave Assignment to the 301-eV Neutron Resonance of Zirconium-96
M. D. Ricabarra
Nuclear Science and Engineering | Volume 48 | Number 3 | July 1972 | Page 370
Technical Note | doi.org/10.13182/NSE72-A22499
Comments on Transfer Scattering Reactor Kinetics
Raphael Aronson
Nuclear Science and Engineering | Volume 48 | Number 3 | July 1972 | Pages 370-371
Technical Note | doi.org/10.13182/NSE72-A22500
Reply to “Comments on Transfer-Scattering Reactor Kinetics”
H. L. Dodds, Jr., J. C. Robinson, A. R. Buhl
Nuclear Science and Engineering | Volume 48 | Number 3 | July 1972 | Page 371
Technical Note | doi.org/10.13182/NSE72-A22501
Comments on Variational Flux Synthesis Methods for Multigroup Neutron Diffusion Theory
S. Nakamura
Nuclear Science and Engineering | Volume 48 | Number 3 | July 1972 | Pages 371-372
Technical Note | doi.org/10.13182/NSE72-A22502
Reply to “Comments on Variational Flux Synthesis Methods for Multigroup Neutron Diffusion Theory”
Weston M. Stacey, Jr.
Nuclear Science and Engineering | Volume 48 | Number 3 | July 1972 | Page 372
Technical Note | doi.org/10.13182/NSE72-A22503
Application of a Two-Region Heavy Charged Particle Model to Noble-Gas Plasmas Induced by Nuclear Radiations
J. C. Guyot, G. H. Miley, J. T. Verdeyen
Nuclear Science and Engineering | Volume 48 | Number 4 | August 1972 | Pages 373-386
Technical Paper | doi.org/10.13182/NSE72-A22505
Explosive Interaction of Molten Metals Injected Into Water
R. H. Bradley, L. C. Witte
Nuclear Science and Engineering | Volume 48 | Number 4 | August 1972 | Pages 387-396
Technical Paper | doi.org/10.13182/NSE72-A22506
Analysis of Inertial Contribution of the Fluid in a Plenum to a Rapid Coolant-Expulsion Process in a Liquid Metal Fast Breeder Reactor Single-Subassembly Accident
T. C. Chawla
Nuclear Science and Engineering | Volume 48 | Number 4 | August 1972 | Pages 397-402
Technical Paper | doi.org/10.13182/NSE72-A22507
Monte Carlo Sampling with Continuously Varying Cross Sections Along Flight Paths
L. L. Carter, E. D. Cashwell, W. M. Taylor
Nuclear Science and Engineering | Volume 48 | Number 4 | August 1972 | Pages 403-411
Technical Paper | doi.org/10.13182/NSE72-1
Fission Cross Sections of Neptunium-237 from 20 eV to 7 MeV Determined from a Nuclear-Explosive Experiment
R. J. Jiacoletti, W. K. Brown, H. G. Olson
Nuclear Science and Engineering | Volume 48 | Number 4 | August 1972 | Pages 412-419
Technical Paper | doi.org/10.13182/NSE72-A22509
Albedo and Milne’s Problems for Thermal Neutrons - II
S. Pahor, H. A. Larson
Nuclear Science and Engineering | Volume 48 | Number 4 | August 1972 | Pages 420-432
Technical Paper | doi.org/10.13182/NSE72-A22510
Homogeneous Critical Assemblies of 2 and 3% Uranium-235-Enriched Uranium in Paraffin
S. J. Raffety, J. T. Mihalczo
Nuclear Science and Engineering | Volume 48 | Number 4 | August 1972 | Pages 433-443
Technical Paper | doi.org/10.13182/NSE72-A22511
Variational Estimates of Reactivity Worths and Reaction Rate Ratios in Critical Nuclear Reactors
Nuclear Science and Engineering | Volume 48 | Number 4 | August 1972 | Pages 444-458
Technical Paper | doi.org/10.13182/NSE72-A22512
A One-Group Method for Fast Reactor Calculations
M. K. Sheaffer, M. J. Driscoll, I. Kaplan
Nuclear Science and Engineering | Volume 48 | Number 4 | August 1972 | Pages 459-466
Technical Paper | doi.org/10.13182/NSE72-A22513
Analyses of Temperature and Power Noise in Operating Nuclear Reactors
Keiichi Saito
Nuclear Science and Engineering | Volume 48 | Number 4 | August 1972 | Pages 467-474
Technical Paper | doi.org/10.13182/NSE72-A22514