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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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!
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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.
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Analysis of Measured Total Pressures from Irradiated Solid and Liquid (U,Pu)-Mixed Oxide
W. Breitung
Nuclear Science and Engineering | Volume 108 | Number 1 | May 1991 | Pages 1-15
Technical Paper | doi.org/10.13182/NSE91-A23804
Forward and Adjoint Methods and Applications for Deterministic Electron-Photon Transport
C. R. Drumm, W. C. Fan, J. H. Renken
Nuclear Science and Engineering | Volume 108 | Number 1 | May 1991 | Pages 16-49
Technical Paper | doi.org/10.13182/NSE91-A23805
On the Slowing Down and Transport of Neutrons in an Infinite Medium
Dan G. Cacuci
Nuclear Science and Engineering | Volume 108 | Number 1 | May 1991 | Pages 50-68
Technical Paper | doi.org/10.13182/NSE91-A23806
Temperature Jump: Rigid-Sphere Gas with Arbitrary Gas/Surface Interaction
S. K. Loyalka
Nuclear Science and Engineering | Volume 108 | Number 1 | May 1991 | Pages 69-73
Technical Paper | doi.org/10.13182/NSE91-A23807
Derivatives for the Equations of State of Multicomponent Mixtures for Universal Multicomponent Flow Models
N. I. Kolev
Nuclear Science and Engineering | Volume 108 | Number 1 | May 1991 | Pages 74-87
Technical Paper | doi.org/10.13182/NSE91-A23808
Vapor Explosions in a Stratified Geometry
K. H. Bang, M. L. Corradini
Nuclear Science and Engineering | Volume 108 | Number 1 | May 1991 | Pages 88-108
Technical Paper | doi.org/10.13182/NSE91-A23809
Calculation of Fission Neutron Spectra for Spontaneous Fission of 240Pu, 238Pu and 242Pu
R. L. Walsh, G. Chircu, D. G. Madland
Nuclear Science and Engineering | Volume 108 | Number 1 | May 1991 | Pages 109-115
Technical Paper | doi.org/10.13182/NSE91-A23810
Calculations of the Production Cross Sections of High-Spin Isomeric States in Hafnium
M. B. Chadwick, P. G. Young
Nuclear Science and Engineering | Volume 108 | Number 2 | June 1991 | Pages 117-125
Technical Paper | doi.org/10.13182/NSE91-A23812
Time-Independent Neutronic Analysis of the Chernobyl Accident
P. A. Landeyro, A. Buccafurni
Nuclear Science and Engineering | Volume 108 | Number 2 | June 1991 | Pages 126-149
Technical Paper | doi.org/10.13182/NSE91-A23813
Reactivity Due to Deformation of a Thin Plate in a Critical Reactor
M. L. Williams
Nuclear Science and Engineering | Volume 108 | Number 2 | June 1991 | Pages 150-171
Technical Paper | doi.org/10.13182/NSE91-A23814
Lower Head Creep-Rupture Sensitivity Studies
Sudip S. Dosanjh, Martin Pilch
Nuclear Science and Engineering | Volume 108 | Number 2 | June 1991 | Pages 172-183
Technical Paper | doi.org/10.13182/NSE91-A23815
Decay of Buoyancy-Driven Stratified Layers with Applications to Pressurized Thermal Shock: Reactor Predictions
K. Iyer, T. G. Theofanous
Nuclear Science and Engineering | Volume 108 | Number 2 | June 1991 | Pages 184-197
Technical Paper | doi.org/10.13182/NSE91-A23816
Flooding-Limited Thermal Mixing: The Case of High Froude Number Injection
Nuclear Science and Engineering | Volume 108 | Number 2 | June 1991 | Pages 198-207
Technical Note | doi.org/10.13182/NSE91-A23817
Probabilities for Lattice Integral Transport
M. Segev, J. Stepanek
Nuclear Science and Engineering | Volume 108 | Number 2 | June 1991 | Pages 208-213
Technical Note | doi.org/10.13182/NSE91-A23818
Surface Current Double-Heterogeneous Multilayer Multicell Methodology
J. Stepanek , M. Segev
Nuclear Science and Engineering | Volume 108 | Number 3 | July 1991 | Pages 215-229
Technical Paper | doi.org/10.13182/NSE91-A23820
Generalization of the Stamm’ler Method for the Self-Shielding of Resonant Isotopes in Arbitrary Geometries
A. Hébert , G. Marleau
Nuclear Science and Engineering | Volume 108 | Number 3 | July 1991 | Pages 230-239
Technical Paper | doi.org/10.13182/NSE90-57
A Monte Carlo Direction Biasing Approach in the Laboratory System for Isotropic Neutron Center-of-Mass Scattering Including Hydrogen
R. P. Gardner, M. Mickael, M. Oraby, K. Verghese
Nuclear Science and Engineering | Volume 108 | Number 3 | July 1991 | Pages 240-246
Technical Paper | doi.org/10.13182/NSE91-A23822
An Analysis of the Finite Differenced, Even-Parity, Discrete Ordinates Equations in Slab Geometry
Warren F. Miller, Jr.
Nuclear Science and Engineering | Volume 108 | Number 3 | July 1991 | Pages 247-266
Technical Paper | doi.org/10.13182/NSE91-A23823
Angular Parallelization of a Curvilinear Sn Transport Theory Method
Alireza Haghighat
Nuclear Science and Engineering | Volume 108 | Number 3 | July 1991 | Pages 267-277
Technical Paper | doi.org/10.13182/NSE91-A23824
Richardson Extrapolation Applied to Difference Methods for Numerically Solving the Neutron Transport Equation in Spherical Geometry
W. E. Abbott, E. J. Allen
Nuclear Science and Engineering | Volume 108 | Number 3 | July 1991 | Pages 278-288
Technical Note | doi.org/10.13182/NSE91-A23825
Cross-Section Measurements of (n,p) and (n,np + pn + d) Reactions for Some Titanium, Chromium, Iron, Cobalt, Nickel, and Zinc Isotopes Around 14 MeV
M. Viennot, M. Berrada, G. Paic, S. Joly
Nuclear Science and Engineering | Volume 108 | Number 3 | July 1991 | Pages 289-301
Technical Note | doi.org/10.13182/NSE87-157
Fast Neutron Radiative Capture Cross Sections of Natural Niobium and Molybdenum
Yunshan Mu, Haishan Xu, Zhengyu Xiang, Yexiang Li, Shiming Wang, Jianfeng Liu
Nuclear Science and Engineering | Volume 108 | Number 3 | July 1991 | Pages 302-307
Technical Note | doi.org/10.13182/NSE91-A23827
Neutron Absorber Effect on Coolant Void Reactivity in a Pressure-Tube-Type Heavy Water Reactor
Yasuki Kowata , Nobuo Fukumura
Nuclear Science and Engineering | Volume 108 | Number 3 | July 1991 | Pages 308-318
Technical Note | doi.org/10.13182/NSE91-A23828
Thermal Neutron Steady-State Spectra in Light Water Reactor Fuel Assemblies Poisoned with Various Non-l/v Absorbers of Different Concentrations
K. Swaminathan, Satish Chandra, R. C. Jha, S. P. Tewari
Nuclear Science and Engineering | Volume 108 | Number 3 | July 1991 | Pages 319-323
Technical Note | doi.org/10.13182/NSE91-A23829
The Effect of Random Material Density on Reactor Criticality
G. C. Pomraning
Nuclear Science and Engineering | Volume 108 | Number 4 | August 1991 | Pages 325-330
Technical Paper | doi.org/10.13182/NSE91-A23831
Noise Analysis Method for Monitoring the Moderator Temperature Coefficient of Pressurized Water Reactors: I. Theory
J. R. Thomas, Jr., J. D. Herr, D. S. Wood
Nuclear Science and Engineering | Volume 108 | Number 4 | August 1991 | Pages 331-340
Technical Paper | doi.org/10.13182/NSE90-42
Noise Analysis Method for Monitoring the Moderator Temperature Coefficient of Pressurized Water Reactors: II. Experimental
J. D. Herr, J. R. Thomas, Jr.
Nuclear Science and Engineering | Volume 108 | Number 4 | August 1991 | Pages 341-346
Technical Paper | doi.org/10.13182/NSE90-43
Feedback Theory for Linear Reactivity Transients in a Point Reactor
Takeo Nishigori
Nuclear Science and Engineering | Volume 108 | Number 4 | August 1991 | Pages 347-354
Technical Paper | doi.org/10.13182/NSE91-A23834
Generalized Contributon Response Theory
Nuclear Science and Engineering | Volume 108 | Number 4 | August 1991 | Pages 355-383
Technical Paper | doi.org/10.13182/NSE90-33
The Maximum Entropy Method for Reconstruction of the Pointwise Neutron Flux Distribution in Nodal Methods
Woo Sik Jung, Nam Zin Cho
Nuclear Science and Engineering | Volume 108 | Number 4 | August 1991 | Pages 384-395
Technical Paper | doi.org/10.13182/NSE91-A23836
A New Critical Heat Flux Correlation for Boiling Liquid Metals
H. M. Kottowski, C. Savatteri, W. Hufschmidt
Nuclear Science and Engineering | Volume 108 | Number 4 | August 1991 | Pages 396-413
Technical Paper | doi.org/10.13182/NSE91-A23837
Effective Atomic Numbers for Total Gamma-Ray Interaction and Incoherent Scattering in Some Alloys at 662 keV
Ashok Madiyal, I. Vasudeva Rao, N. Lingappa, K. Siddappa
Nuclear Science and Engineering | Volume 108 | Number 4 | August 1991 | Pages 414-418
Technical Paper | doi.org/10.13182/NSE91-A23838
