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Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
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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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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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The Matching of Dense Plasma Focus Devices with Fission Reactors
A. A. Harms, M. Heindler
Nuclear Science and Engineering | Volume 66 | Number 1 | April 1978 | Pages 1-8
Technical Paper | doi.org/10.13182/NSE78-A15182
Optimum Supervision Intervals and Order of Supervision in Nuclear Reactor Protective Systems
J. M. Kontoleon
Nuclear Science and Engineering | Volume 66 | Number 1 | April 1978 | Pages 9-13
Technical Paper | doi.org/10.13182/NSE78-A15183
Probabilistic Accident Analysis with Deterministic Codes Using Stochastically Variable Parameters
P. B. Abramson, H. H. Hummel, E. M. Gelbard, P. A. Pizzica, J. J. Sienicki
Nuclear Science and Engineering | Volume 66 | Number 1 | April 1978 | Pages 14-23
Technical Paper | doi.org/10.13182/NSE78-A15184
Angular Distribution of Fission Fragments from Fast Fission of Uranium-235
S. T. Hsue, G. F. Knoll, J. Meadows
Nuclear Science and Engineering | Volume 66 | Number 1 | April 1978 | Pages 24-28
Technical Paper | doi.org/10.13182/NSE78-A15185
Determination of Reactivity from Power Spectral Density Measurements with Californium-252
J. T. Mihalczo, V. K. Paré, G. L. Ragan, M. V. Mathis, G. C. Tillett
Nuclear Science and Engineering | Volume 66 | Number 1 | April 1978 | Pages 29-59
Technical Paper | doi.org/10.13182/NSE78-A15186
A Monte Carlo Perturbation Source Method for Reactivity Calculations
T. J. Hoffman, L. M. Petrie, N. F. Landers
Nuclear Science and Engineering | Volume 66 | Number 1 | April 1978 | Pages 60-66
Technical Paper | doi.org/10.13182/NSE78-A15187
Calculation of the Reactivity due to Bubble Collapse with the Probability Table Method
T. J. Hoffman, L. M. Petrie
Nuclear Science and Engineering | Volume 66 | Number 1 | April 1978 | Pages 67-74
Technical Paper | doi.org/10.13182/NSE78-A15188
Gamma-Ray Production Cross Sections of Neutron-Induced Reactions in Oxygen
C. Nordborg, L. Nilsson, H. Condé, L. G. Strömberg
Nuclear Science and Engineering | Volume 66 | Number 1 | April 1978 | Pages 75-83
Technical Paper | doi.org/10.13182/NSE78-A15189
Finite Element Analysis for Turbulent Flows of Incompressible Fluids in Fuel Rod Bundles
W. Slagter
Nuclear Science and Engineering | Volume 66 | Number 1 | April 1978 | Pages 84-92
Technical Paper | doi.org/10.13182/NSE78-A15190
Characteristics, Stability, and Short-Wavelength Phenomena in Two-Phase Flow Equation Systems
John D. Ramshaw, John A. Trapp
Nuclear Science and Engineering | Volume 66 | Number 1 | April 1978 | Pages 93-102
Technical Paper | doi.org/10.13182/NSE78-A15191
Experimental Investigation of Gas Evolution as the Mechanism for Free-Contact Fragmentation
G. Shiralker, W. Rohsenow, A. Sonin, N. Todreas
Nuclear Science and Engineering | Volume 66 | Number 1 | April 1978 | Pages 103-109
Technical Paper | doi.org/10.13182/NSE78-A15192
The Oxidation and Degradation of Short-Chain Aliphatic Compounds by Hyperazeotropic Nitric Acid
Walter E. Clark, W. B. Howerton, B. M. Benjamin, W. H. Baldwin
Nuclear Science and Engineering | Volume 66 | Number 1 | April 1978 | Pages 110-117
Technical Paper | doi.org/10.13182/NSE78-A15193
A Semi-Analytic Solution to the Transport Equation in Spherical Geometry
A. Dubi, Y. S. Horowitz
Nuclear Science and Engineering | Volume 66 | Number 1 | April 1978 | Pages 118-121
Technical Note | doi.org/10.13182/NSE78-A15194
General Formulation of Track-Length-Type Estimators
I. Lux
Nuclear Science and Engineering | Volume 66 | Number 1 | April 1978 | Pages 121-124
Technical Note | doi.org/10.13182/NSE78-A15195
Applications of the Upper Bound Estimation Method in Reactor Theory
Yigal Ronen, Dror Regev
Nuclear Science and Engineering | Volume 66 | Number 1 | April 1978 | Pages 124-127
Technical Note | doi.org/10.13182/NSE78-A15196
Thermal Westcott g-Factor Measurement for Thorium-232
L. Green
Nuclear Science and Engineering | Volume 66 | Number 1 | April 1978 | Pages 127-134
Technical Note | doi.org/10.13182/NSE78-A15197
A Multigroup Formalism for Evaluation of Continuous Slowing Down Theory Parameters
Ansar Parvez, Martin Becker
Nuclear Science and Engineering | Volume 66 | Number 1 | April 1978 | Pages 134-140
Technical Note | doi.org/10.13182/NSE78-A15198
Modeling the Effect of Fission Product Capture on Reactor Decay Power
B. I. Spinrad, A. Tripathi
Nuclear Science and Engineering | Volume 66 | Number 1 | April 1978 | Pages 140-141
Technical Note | doi.org/10.13182/NSE78-A15199
Note on 238U + n Resolved Resonance Energies
D. K. Olsen, G. de Saussure, R. B. Perez, F. C. Difilippo, and R. W. Ingle
Nuclear Science and Engineering | Volume 66 | Number 1 | April 1978 | Pages 141-144
Technical Note | doi.org/10.13182/NSE78-A15200
Critical Impurity Concentrations for Ignition of Catalyzed-Deuterium Fusion Plasmas
R. V. Jensen, D. L. Jassby, D. E. Post
Nuclear Science and Engineering | Volume 66 | Number 1 | April 1978 | Pages 144-146
Technical Note | doi.org/10.13182/NSE78-A15201
An Experimental Study of the Molten Glass/Water Thermal Interaction Under Free and Forced Conditions
V. H. Arakeri, I. Catton, and W. E. Kastenberg
Nuclear Science and Engineering | Volume 66 | Number 2 | May 1978 | Pages 153-166
Technical Paper | doi.org/10.13182/NSE78-A27197
Fissile Fuel Doubling Time Characteristics for Reactor Lifetime Fuel Logistics
M. Heindler and A. A. Harms
Nuclear Science and Engineering | Volume 66 | Number 2 | May 1978 | Pages 167-187
Technical Paper | doi.org/10.13182/NSE78-A27198
Cross Sections for the 11B(α, p)14C Reaction in the Alpha-Particle Energy Range from 4.4 to 6.7 MeV
Wen-Sou Hou, Chia-Shou Lin, Ming Wen, Hsiao-Hua Hsu, and Jen-Chang Chou
Nuclear Science and Engineering | Volume 66 | Number 2 | May 1978 | Pages 188-192
Technical Paper | doi.org/10.13182/NSE78-A27199
Spectral Fine-Structure Effects in the Reactivity-Reaction-Rate Method for Determining Capture-to-Fission Ratios
E. Greenspan, Y. Karni
Nuclear Science and Engineering | Volume 66 | Number 2 | May 1978 | Pages 193-204
Technical Paper | doi.org/10.13182/NSE78-A27200
Measurement of the Fission Cross Sections of Uranium-233 and Plutonium-239 Relative to Uranium-235 from 1 keV to 30 MeV
G. W. Carlson and J. W. Behrens
Nuclear Science and Engineering | Volume 66 | Number 2 | May 1978 | Pages 205-216
Technical Paper | doi.org/10.13182/NSE78-1
Neutron Capture Probabilities for Thick Samples at Resonance Energies
Makio Ohkubo
Nuclear Science and Engineering | Volume 66 | Number 2 | May 1978 | Pages 217-228
Technical Paper | doi.org/10.13182/NSE78-A27202
The Importance Factor of a Source in Reactor Kinetics
J. Ligou
Nuclear Science and Engineering | Volume 66 | Number 2 | May 1978 | Pages 229-234
Technical Paper | doi.org/10.13182/NSE78-A27203
Polynomial Approach to Reactor Kinetics Equations
Kueng Yeh
Nuclear Science and Engineering | Volume 66 | Number 2 | May 1978 | Pages 235-242
Technical Paper | doi.org/10.13182/NSE78-A27204
Cross-Section Sensitivity Analysis of 235U and 238U Fission Rates Measured in a Graphite-Reflected Lithium Assembly
Yasushi Seki and Hiroshi Maekawa
Nuclear Science and Engineering | Volume 66 | Number 2 | May 1978 | Pages 243-251
Technical Note | doi.org/10.13182/NSE78-A27205
Extension of the Width Fluctuation Correction to Reactions Involving Continuum Level Excitations
G. Reffo and F. Fabbri
Nuclear Science and Engineering | Volume 66 | Number 2 | May 1978 | Pages 251-254
Technical Note | doi.org/10.13182/NSE78-A27206
On Approximations to the Neutron Escape Probability from an Absorbing Body
Yung-An Chao, Aquilino Senra Martinez
Nuclear Science and Engineering | Volume 66 | Number 2 | May 1978 | Pages 254-258
Technical Note | doi.org/10.13182/NSE66-254
Remark on the Efficiency of Track-Length Estimators in Reaction Rate Estimations
Nuclear Science and Engineering | Volume 66 | Number 2 | May 1978 | Pages 258-264
Technical Note | doi.org/10.13182/NSE78-A27208
Determination of Void Fraction Profile in a Boiling Water Reactor Channel Using Neutron Noise Analysis
M. Ashraf Atta, D. N. Fry, J. E. Mott, and W. T. King
Nuclear Science and Engineering | Volume 66 | Number 2 | May 1978 | Pages 264-268
Technical Note | doi.org/10.13182/NSE78-A27209
Higher Order Prompt-Jump Approximation in Reactor Kinetics
Tomasz Błeński, Adam Gadomski, Janusz Mika
Nuclear Science and Engineering | Volume 66 | Number 3 | June 1978 | Pages 277-283
Technical Paper | doi.org/10.13182/NSE78-A27212
Analysis of the Eigenvalue Equations in k, λ, γ, and α Applied to Some Fast- and Thermal-Neutron Systems
Guillermo Velarde, Carolina Ahnert, José M. Aragonés
Nuclear Science and Engineering | Volume 66 | Number 3 | June 1978 | Pages 284-294
Technical Paper | doi.org/10.13182/NSE78-A27213
Polynomial Solutions to the Tensorial Differential Equations for Monoenergetic Neutrons in Slab and Sphere Geometries
P. Landini, G. Spiga, F. Premuda
Nuclear Science and Engineering | Volume 66 | Number 3 | June 1978 | Pages 295-306
Technical Paper | doi.org/10.13182/NSE78-A27214
Application of Sensitivity and Uncertainty Methodology to Fast Reactor Integral Experiment Analysis
C. R. Weisbin, E. M. Oblow, J. H. Marable, R. W. Peelle, J. L. Lucius
Nuclear Science and Engineering | Volume 66 | Number 3 | June 1978 | Pages 307-333
Technical Paper | doi.org/10.13182/NSE78-3
Calculation of Nuclear Level Densities for 56Fe, 59Co, 60Ni, 61Cu, 62Ni, 63Cu, and 65Cu
G. P. Ford
Nuclear Science and Engineering | Volume 66 | Number 3 | June 1978 | Pages 334-348
Technical Paper | doi.org/10.13182/NSE78-A27216
Precise Measurement of the Capture Width of the 6.67-eV Neutron Resonance of Uranium-238
P. Staveloz, F. Poortmans, L. Mewissen, E. Cornelis
Nuclear Science and Engineering | Volume 66 | Number 3 | June 1978 | Pages 349-353
Technical Paper | doi.org/10.13182/NSE78-A27217
Measurement and Calculation of Californium-252 Fission Neutron-Induced Gamma Fields in Iron
S. H. Jiang, H. Werle
Nuclear Science and Engineering | Volume 66 | Number 3 | June 1978 | Pages 354-362
Technical Paper | doi.org/10.13182/NSE78-A27218
Neutron Capture Cross-Section Ratios of 240Pu, 242Pu, 238U, and 197Au in the Energy Range from 10 to 90 keV
K. Wisshak, F. Käppeler
Nuclear Science and Engineering | Volume 66 | Number 3 | June 1978 | Pages 363-377
Technical Paper | doi.org/10.13182/NSE78-A27219
Characteristics and Stability Analyses of Transient One-Dimensional Two-Phase Flow Equations and Their Finite Difference Approximations
Robert W. Lyczkowski, Dimitri Gidaspow, Charles W. Solbrig, E. D. Hughes
Nuclear Science and Engineering | Volume 66 | Number 3 | June 1978 | Pages 378-396
Technical Paper | doi.org/10.13182/NSE78-4
Effects of Internal Circulation Velocity and Noncondensable Gas on Vapor Condensation from a Rising Bubble
M. N. Özişik, T. S. Kress
Nuclear Science and Engineering | Volume 66 | Number 3 | June 1978 | Pages 397-405
Technical Paper | doi.org/10.13182/NSE78-A27221
Self-Diffusion Processes in Nuclear Carbonitrides UCxN1 − x and (U, Pu)C0.8N0.2
H. Matsui, M. H. Bradbury, Hj. Matzke
Nuclear Science and Engineering | Volume 66 | Number 3 | June 1978 | Pages 406-414
Technical Paper | doi.org/10.13182/NSE78-A27222
Fast Power Excursions in Pebble-Bed Reactors—Methods and Results
K. Friedrich, E. Inführ, U. Weicht
Nuclear Science and Engineering | Volume 66 | Number 3 | June 1978 | Pages 415-421
Technical Note | doi.org/10.13182/NSE78-A27223
A General Correlation for Independent Fission Product Yield Uncertainties
B. I. Spinrad, C. H. Wu
Nuclear Science and Engineering | Volume 66 | Number 3 | June 1978 | Pages 421-424
Technical Note | doi.org/10.13182/NSE78-A27224
Evaluation of the Neutron Flux-Depression Factor via the Integral Transform Method
V. C. Boffi, V. G. Molinari, G. Spiga
Nuclear Science and Engineering | Volume 66 | Number 3 | June 1978 | Pages 424-428
Technical Note | doi.org/10.13182/NSE78-A27225
Transport of Neutron and Secondary Gamma Radiations Through a Liquid Air Sphere Surrounding a 14-MeV Neutron Source
G. S. Sidhu, W. E. Farley, L. F. Hansen, T. Komoto, B. Pohl, C. Wong
Nuclear Science and Engineering | Volume 66 | Number 3 | June 1978 | Pages 428-433
Technical Note | doi.org/10.13182/NSE78-A27226
Measurements of the Neutron-Induced Fission Cross Sections of 240Pu, 242Pu, and 244Pu Relative to 235U from 0.1 to 30 MeV
J. W. Behrens, R. S. Newbury, J. W. Magana
Nuclear Science and Engineering | Volume 66 | Number 3 | June 1978 | Pages 433-441
Technical Note | doi.org/10.13182/NSE78-A27227
6Li + 6Li ⇒ 34He Cross Sections and Thermonuclear Fusion Parameters
E. Norbeck
Nuclear Science and Engineering | Volume 66 | Number 3 | June 1978 | Pages 441-444
Technical Note | doi.org/10.13182/NSE78-A27228
