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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
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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Wyoming OKs construction of TerraPower’s Natrium plant
Progress continues for TerraPower’s Natrium plant, with the latest win coming in the form of a state permit for construction of nonnuclear portions of the advanced reactor.
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Rate of Liquid Entrainment at the Gas-Liquid Interface of a Liquid Submerged Sonic Gas Jet
T. C. Chawla
Nuclear Science and Engineering | Volume 56 | Number 1 | January 1975 | Pages 1-6
Technical Paper | doi.org/10.13182/NSE75-A26616
A Computational Technique to Assess Procedures for Failed-Fuel Identification
N. J. McCormick
Nuclear Science and Engineering | Volume 56 | Number 1 | January 1975 | Pages 7-15
Technical Paper | doi.org/10.13182/NSE75-A26617
Joint Probability Distribution of Neutron Counts in Reactor Noise Analysis
M. Marseguerra
Nuclear Science and Engineering | Volume 56 | Number 1 | January 1975 | Pages 16-26
Technical Paper | doi.org/10.13182/NSE75-A26618
Total Neutron Cross Section of Carbon from 1 keV to 15 MeV
H. T. Heaton, II, J. L. Menke, R. A. Schrack, R. B. Schwartz
Nuclear Science and Engineering | Volume 56 | Number 1 | January 1975 | Pages 27-36
Technical Paper | doi.org/10.13182/NSE75-A26619
Delayed-Neutron Data for Reactor-Physics Analysis
R. J. Tuttle
Nuclear Science and Engineering | Volume 56 | Number 1 | January 1975 | Pages 37-71
Technical Paper | doi.org/10.13182/NSE75-A26620
A Theory of Resonance-Group Self-Shielding
M. Segev
Nuclear Science and Engineering | Volume 56 | Number 1 | January 1975 | Pages 72-82
Technical Paper | doi.org/10.13182/NSE75-A26621
Thermonuclear Microfission
F. Winterberg
Nuclear Science and Engineering | Volume 56 | Number 1 | January 1975 | Pages 83-84
Technical Note | doi.org/10.13182/NSE75-A26622
Compact Tables of Functions for Use in Shielding Calculations
K. Shure, O. J. Wallace
Nuclear Science and Engineering | Volume 56 | Number 1 | January 1975 | Pages 84-94
Technical Note | doi.org/10.13182/NSE75-A26623
A New Measurement of the 10B(n, α)7Li Branching Ratio
G. P. Lamaze, A. D. Carlson, M. M. Meier
Nuclear Science and Engineering | Volume 56 | Number 1 | January 1975 | Pages 94-96
Technical Note | doi.org/10.13182/NSE75-A26624
Calculated Nickel-58 Reaction Cross Sections Around 14-MeV Neutron Energy
B. S. Wadhwa, R. K. Mohindra
Nuclear Science and Engineering | Volume 56 | Number 1 | January 1975 | Pages 96-98
Technical Note | doi.org/10.13182/NSE75-A26625
Measured Thermal-Neutron Cross Section for the 59Ni(n, α)56Fe Reaction
R. D. Werner, D. C. Santry
Nuclear Science and Engineering | Volume 56 | Number 1 | January 1975 | Pages 98-100
Technical Note | doi.org/10.13182/NSE75-A26626
A Generalized Source-Multiplication Method for Determining Reactivity
Ehud Greenspan
Nuclear Science and Engineering | Volume 56 | Number 1 | January 1975 | Pages 100-103
Technical Note | doi.org/10.13182/NSE75-A26627
A Source-Multiplication Reactivity
Nuclear Science and Engineering | Volume 56 | Number 1 | January 1975 | Pages 103-106
Technical Note | doi.org/10.13182/NSE75-A26628
An Improved Series Representation of Doppler-Broadened Resonance Absorption
Arthur Ginsberg, Martin Becker
Nuclear Science and Engineering | Volume 56 | Number 1 | January 1975 | Pages 106-107
Technical Note | doi.org/10.13182/NSE75-A26629
A Generalized Perturbation Theory and Variational Principle for Multiple Ratios of Linear and Bilinear Functionals
Nuclear Science and Engineering | Volume 56 | Number 1 | January 1975 | Pages 107-112
Technical Note | doi.org/10.13182/NSE75-A26630
Characteristics of Uncertainties in Sensitivity Studies of Fast-Reactor Parameters
R. N. Hwang
Nuclear Science and Engineering | Volume 56 | Number 2 | February 1975 | Pages 119-130
Technical Paper | doi.org/10.13182/NSE75-A26651
A Higher Order Relationship Between Static Power Tilts and Eigenvalue Separation in Nuclear Reactors
W. D. Beckner, R. A. Rydin
Nuclear Science and Engineering | Volume 56 | Number 2 | February 1975 | Pages 131-141
Technical Paper | doi.org/10.13182/NSE75-A26652
Application of Artificial Intelligence Techniques to Digital Computer Control of Nuclear Reactors
ames L. Macdonald, Billy V. Koen
Nuclear Science and Engineering | Volume 56 | Number 2 | February 1975 | Pages 142-151
Technical Paper | doi.org/10.13182/NSE75-A26653
Computational Models for the Study of Azimuthally Dependent Disassembly of Liquid-Metal Fast Breeder Reactors
Paul B. Bleiweis, William E. Kastenberg, David Okrent
Nuclear Science and Engineering | Volume 56 | Number 2 | February 1975 | Pages 152-170
Technical Paper | doi.org/10.13182/NSE75-A26654
Tabulation and Empirical Representation of Infinite-Medium Gamma-Ray Buildup Factors for Monoenergetic, Point Isotropic Sources in Water, Aluminum, and Concrete
E. E. MORRIS, A. B. CHILTON, A. F VETTER
Nuclear Science and Engineering | Volume 56 | Number 2 | February 1975 | Pages 171-178
Technical Paper | doi.org/10.13182/NSE75-A26655
Experimental Determination of Photofission Neutron Multiplicities for Eight Isotopes in the Mass Range 232 ≤ A ≤ 239
J. T. Caldwell and E. J. Dowdy
Nuclear Science and Engineering | Volume 56 | Number 2 | February 1975 | Pages 179-187
Technical Paper | doi.org/10.13182/NSE75-A26656
A Thermal Analysis of Hot Spots on Fast-Reactor Fuel Cladding Due to Deposition of Low-Conductivity Materials
M. Ishii, T. C. Chawla
Nuclear Science and Engineering | Volume 56 | Number 2 | February 1975 | Pages 188-195
Technical Paper | doi.org/10.13182/NSE75-A26657
Atmospheric Stability Inside Containments with a Heated Layer of Liquid on the Floor
Joh. F. van de Vate, A. Plomp
Nuclear Science and Engineering | Volume 56 | Number 2 | February 1975 | Pages 196-200
Technical Paper | doi.org/10.13182/NSE75-A26658
Partial Wave Expansion of the Induced Collision Kernel
B. R. Wienke
Nuclear Science and Engineering | Volume 56 | Number 2 | February 1975 | Pages 201-202
Technical Note | doi.org/10.13182/NSE75-A26659
Practical Preprocessed Nuclear Data Files for Fast Reactor Calculations
Y. Gur, S. Yiftah
Nuclear Science and Engineering | Volume 56 | Number 2 | February 1975 | Pages 202-210
Technical Note | doi.org/10.13182/NSE75-A26660
Subcritical Reactivity as Determined from Reactor Noise
Hsiao-Kang Wang, Lawrence Ruby
Nuclear Science and Engineering | Volume 56 | Number 2 | February 1975 | Pages 211-212
Technical Note | doi.org/10.13182/NSE75-A26661
Reactivity from Power Spectral Density Measurements with Californium-252
V. K. Paré, J. T. Mihalczo
Nuclear Science and Engineering | Volume 56 | Number 2 | February 1975 | Pages 213-218
Technical Note | doi.org/10.13182/NSE75-A26662
Direct Sampling from the Klein-Nishina Distribution for Photon Energies Above 1.4 MeV
László Koblinger
Nuclear Science and Engineering | Volume 56 | Number 2 | February 1975 | Pages 218-219
Technical Note | doi.org/10.13182/NSE75-A26663
Additional Few-Group and Multigroup Calculations of Neutron Penetration
K. Shure
Nuclear Science and Engineering | Volume 56 | Number 2 | February 1975 | Pages 219-224
Technical Note | doi.org/10.13182/NSE75-A26664
An In-Pile Study of Thermal Interactions Between . High-Energy Molten UO2 Fuel and Liquid Sodium
S. M. Zivi, M. Epstein, R. W. Wright, J. J. Barghusen, D. H. Cho, F. J. Testa, G. T. Goldfuss, R. W. Mouring
Nuclear Science and Engineering | Volume 56 | Number 3 | March 1975 | Pages 229-240
Technical Paper | doi.org/10.13182/NSE75-A26737
Measured and Calculated Rates of Decay Heat in Irradiated 235U, 233U, 239Pu, and 232Th
S. B. Gunst, D. E. Conway, J. C. Connor
Nuclear Science and Engineering | Volume 56 | Number 3 | March 1975 | Pages 241-262
Technical Paper | doi.org/10.13182/NSE75-A26738
Point Isotropic Gamma-Ray Buildup Factors in Concrete
C. M. Eisenhauer, G. L. Simmons
Nuclear Science and Engineering | Volume 56 | Number 3 | March 1975 | Pages 263-270
Technical Paper | doi.org/10.13182/NSE75-A26739
Neutron Importance and Fission Density in Uranium-235-Enriched Uranium and Plutonium Metal Spheres
J. T. Mihalczo
Nuclear Science and Engineering | Volume 56 | Number 3 | March 1975 | Pages 271-290
Technical Paper | doi.org/10.13182/NSE75-3
Response Matrices in Space-Time Reactor Dynamics
J. M. Sicilian
Nuclear Science and Engineering | Volume 56 | Number 3 | March 1975 | Pages 291-300
Technical Paper | doi.org/10.13182/NSE75-2
Laser-Induced Thermonuclear Micro-Explosions Using Fissionable Triggers
W. Seifritz, J. Ligou
Nuclear Science and Engineering | Volume 56 | Number 3 | March 1975 | Pages 301-303
Technical Note | doi.org/10.13182/NSE75-A26742
The EBR-I Incident: A Reexamination
Gerald S. Lellouche
Nuclear Science and Engineering | Volume 56 | Number 3 | March 1975 | Pages 303-307
Technical Note | doi.org/10.13182/NSE75-A26743
An Assessment of ENDF/B-III Data for Uranium-238 Based on Integral Spectrum Measurements
Martin Becker, Narinder N. Kaushal
Nuclear Science and Engineering | Volume 56 | Number 3 | March 1975 | Pages 307-309
Technical Note | doi.org/10.13182/NSE75-A26744
Diregionally Discontinuous Harmonic Solutions of the Neutron Transport Equation in Spherical Geometry
A. A. Harms, E. A. Attia
Nuclear Science and Engineering | Volume 56 | Number 3 | March 1975 | Pages 310-317
Technical Note | doi.org/10.13182/NSE75-A26745
A Numerical Method for Solving Integral Equations of Neutron Transport
S. K. Loyalka
Nuclear Science and Engineering | Volume 56 | Number 3 | March 1975 | Pages 317-319
Technical Note | doi.org/10.13182/NSE75-2
A Generalized Diffusion Theory for Calculating the Neutron Transport Scalar Flux
Raymond E. Alcouffe
Nuclear Science and Engineering | Volume 56 | Number 4 | April 1975 | Pages 321-339
Technical Paper | doi.org/10.13182/NSE75-A26680
Variational Functionals Which Admit Discontinuous Trial Functions
Paul Nelson, Jr.
Nuclear Science and Engineering | Volume 56 | Number 4 | April 1975 | Pages 340-353
Technical Paper | doi.org/10.13182/NSE75-A26681
Nonlinear Oscillations in a Reactor with Two Temperature Coefficients
James P. Keener, Donald S. Cohen
Nuclear Science and Engineering | Volume 56 | Number 4 | April 1975 | Pages 354-359
Technical Paper | doi.org/10.13182/NSE75-A26682
Calculational Methods for Nuclear Heating-Part I: Theoretical and Computational Algorithms
M. A. Abdou, C. W. Maynard
Nuclear Science and Engineering | Volume 56 | Number 4 | April 1975 | Pages 360-380
Technical Paper | doi.org/10.13182/NSE75-A26683
Calculational Methods for Nuclear Heating—Part II: Applications to Fusion-Reactor Blankets and Shields
Nuclear Science and Engineering | Volume 56 | Number 4 | April 1975 | Pages 381-398
Technical Paper | doi.org/10.13182/NSE75-A26684
Removal of Iodide from LiF-BeF2 Melts by HF-H2 Sparging—An Application to Iodine Removal from Molten Salt Breeder Reactor Fuel
C. F. Baes, Jr., R. P. Wichner, C. E. Bamberger, B. F. Freasier
Nuclear Science and Engineering | Volume 56 | Number 4 | April 1975 | Pages 399-410
Technical Paper | doi.org/10.13182/NSE75-A26685
Transmission Probability Method of Integral Neutron Transport Calculation for Two-Dimensional Rectangular Cells
Hans Häggblom, Åke Ahlin, Takashi Nakamura
Nuclear Science and Engineering | Volume 56 | Number 4 | April 1975 | Pages 411-422
Technical Note | doi.org/10.13182/NSE75-A26686
Zero-Power Noise Analysis in a Reactor with Two Weakly Coupled Asymmetrical Fission Zones
Eckart Viehl
Nuclear Science and Engineering | Volume 56 | Number 4 | April 1975 | Pages 422-427
Technical Note | doi.org/10.13182/NSE75-A26687
A Benchmark Experiment of Neutron Propagation in Iron Used to Test ENDF/B Cross-Section Data
M. Martini, G. Palmiotti, M. Salvatores
Nuclear Science and Engineering | Volume 56 | Number 4 | April 1975 | Pages 427-430
Technical Note | doi.org/10.13182/NSE75-A26688
Power Reactor Calculations with the Finite Element Program FEM 2D
F. A. R. Schmidt, H. P. Franke
Nuclear Science and Engineering | Volume 56 | Number 4 | April 1975 | Pages 431-433
Technical Note | doi.org/10.13182/NSE75-A26689
