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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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A Multiple Balance Approach for Differencing the Sn Equations
J. E. Morel, Edward W. Larsen
Nuclear Science and Engineering | Volume 105 | Number 1 | May 1990 | Pages 1-15
Technical Paper | doi.org/10.13182/NSE90-A19208
Discrete Nodal and Sn Transport Methods for Irregularly Shaped Shields
Sung T. Kim, J. J. Doming
Nuclear Science and Engineering | Volume 105 | Number 1 | May 1990 | Pages 16-30
Technical Paper | doi.org/10.13182/NSE90-A19209
Stability Analysis of Coarse-Mesh Rebalance
Gregory R. Cefus, Edward W. Larsen
Nuclear Science and Engineering | Volume 105 | Number 1 | May 1990 | Pages 31-39
Technical Paper | doi.org/10.13182/NSE88-117
Vectorization of Diffusion Computations in the Presence of Periodic Boundary Conditions
I. K. Abu-Shumays
Nuclear Science and Engineering | Volume 105 | Number 1 | May 1990 | Pages 40-51
Technical Paper | doi.org/10.13182/NSE90-A19211
Three-Dimensional Multiregion Sn Solutions of the Spencer-Lewis Electron Transport Equation
W. L. Filippone, S. P. Monahan, S. Woolf, J. C. Garth
Nuclear Science and Engineering | Volume 105 | Number 1 | May 1990 | Pages 52-58
Technical Paper | doi.org/10.13182/NSE90-A19212
The Exact Kernel (I*) Method Applied to the Charged-Particle Transport Equation
Patrick Miazza, Jacques Ligou
Nuclear Science and Engineering | Volume 105 | Number 1 | May 1990 | Pages 59-78
Technical Paper | doi.org/10.13182/NSE90-A19213
Alpha-Particle Transport and Thermonuclear Burn in Mixtures
B. R. Wienke, J. E. Morel
Nuclear Science and Engineering | Volume 105 | Number 1 | May 1990 | Pages 79-87
Technical Paper | doi.org/10.13182/NSE90-A19214
Test Problems in Radiative Transfer Calculations
A. I. Shestakov, D. S. Kershaw, G. B. Zimmerman
Nuclear Science and Engineering | Volume 105 | Number 1 | May 1990 | Pages 88-104
Technical Paper | doi.org/10.13182/NSE90-A19215
Calculation of Fuel Penetration and Freezing in Channels with a Two-Phase Flow Code
Alan V. Jones
Nuclear Science and Engineering | Volume 105 | Number 2 | June 1990 | Pages 105-122
Technical Paper | doi.org/10.13182/NSE90-A23741
Chaotic Dynamics of a Triply-Forced Two-Phase Flow System
Rizwan-uddin, J. J. Dorning
Nuclear Science and Engineering | Volume 105 | Number 2 | June 1990 | Pages 123-135
Technical Paper | doi.org/10.13182/NSE90-A23742
Application of Krylov Subspace Methods in Fluid Dynamics
Hrabri L. Rajic, Youcef Saad
Nuclear Science and Engineering | Volume 105 | Number 2 | June 1990 | Pages 136-141
Technical Paper | doi.org/10.13182/NSE90-A23743
A Rigorous Mathematical Technique for Reactor Dynamics: Application to Safe Plutonium Recycling
S. E. Corno, M. L. Buzano, P. Ravetto
Nuclear Science and Engineering | Volume 105 | Number 2 | June 1990 | Pages 142-159
Technical Paper | doi.org/10.13182/NSE90-A23744
Development of a Technique for the Practical Implementation of Higher Order Perturbation Methods
John R. White, Glenn A. Swanbon
Nuclear Science and Engineering | Volume 105 | Number 2 | June 1990 | Pages 160-173
Technical Paper | doi.org/10.13182/NSE90-A23745
A State Space Search Technique for Optimizing the Shape of a Cold Neutron Source
Y. Y. Azmy
Nuclear Science and Engineering | Volume 105 | Number 2 | June 1990 | Pages 174-183
Technical Paper | doi.org/10.13182/NSE90-A23746
The Multigroup and Cylindrical Geometry Formulation of the Fully Coupled Sn/Monte Carlo Method
R. S. Baker, W. L. Filippone, R. E. Alcouffe
Nuclear Science and Engineering | Volume 105 | Number 2 | June 1990 | Pages 184-190
Technical Paper | doi.org/10.13182/NSE90-A23747
A Diffusion-Accelerated Sn Transport Method for Radiation Transport on a General Quadrilateral Mesh
R. E. Alcouffe
Nuclear Science and Engineering | Volume 105 | Number 2 | June 1990 | Pages 191-197
Technical Paper | doi.org/10.13182/NSE90-A23748
A First-Collision Source Method That Satisfies Discrete Sn Transport Balance
R. E. Alcouffe, R. D. O’Dell, F. W. Brinkley, Jr.
Nuclear Science and Engineering | Volume 105 | Number 2 | June 1990 | Pages 198-203
Technical Paper | doi.org/10.13182/NSE90-A23749
The Density and Compressibility of Liquid (U,Pu)-Mixed Oxide
W. Breitung, K. O. Reil
Nuclear Science and Engineering | Volume 105 | Number 3 | July 1990 | Pages 205-217
Technical Paper | doi.org/10.13182/NSE90-A19186
Neutron Kinetics Investigations at the LR-0 Zero-Power Reactor
V. Rypar, J. Racek, K.-H. Fährmann, U. Grundmann, D. Ziegenbein
Nuclear Science and Engineering | Volume 105 | Number 3 | July 1990 | Pages 218-232
Technical Paper | doi.org/10.13182/NSE90-A19187
Gamma-Ray Activation and Passive Neutron Methods for Nondestructive Assay of Spent-Fuel Assemblies
Zs. Németh, Á. Veres, I. Pavlicsek, L. Lakosi
Nuclear Science and Engineering | Volume 105 | Number 3 | July 1990 | Pages 233-243
Technical Paper | doi.org/10.13182/NSE90-A19188
Analysis of Sample and Fuel Pin Irradiation Experiments in Phénix for Basic Nuclear Data Validation
A. D’Angelo, F. Cleri, P. Marimbeau, M. Salvatores, J. P. Grouiller
Nuclear Science and Engineering | Volume 105 | Number 3 | July 1990 | Pages 244-255
Technical Paper | doi.org/10.13182/NSE90-A19189
Variational Formulation of a Higher Order Nodal Diffusion Method
D. V. Altiparmakov, Dj. Tomašević
Nuclear Science and Engineering | Volume 105 | Number 3 | July 1990 | Pages 256-270
Technical Paper | doi.org/10.13182/NSE90-A19190
Wiener-Hopf Technique Solution to a Rewetting Model with Precursory Cooling
Shmuel Olek
Nuclear Science and Engineering | Volume 105 | Number 3 | July 1990 | Pages 271-277
Technical Paper | doi.org/10.13182/NSE90-A19191
Comparison of Calculated Results with Experimental Data for the Tritium Production Rates in a Li2O Assembly
R. T. Santoro, R. G. Alsmiller, Jr., J. M. Barnes, T. A. Gabriel
Nuclear Science and Engineering | Volume 105 | Number 3 | July 1990 | Pages 278-289
Technical Paper | doi.org/10.13182/NSE90-A19192
A Generalized Perturbation Theory for the Reconstruction of the Axial Offset in a Pressurized Water Reactor
G. B. Bruna, R. Aigle, O. Loussouarn
Nuclear Science and Engineering | Volume 105 | Number 3 | July 1990 | Pages 290-296
Technical Notes | doi.org/10.13182/NSE90-A19193
Simultaneous Estimation of Neutron Density and Reactivity in a Nuclear Reactor Using a Bank of Kalman Filters
Carlos E. D’Attellis, Elsa Cortina
Nuclear Science and Engineering | Volume 105 | Number 3 | July 1990 | Pages 297-299
Technical Notes | doi.org/10.13182/NSE90-A19194
Measurements of the Total Pressure from Irradiated (U,Pu)-Mixed Oxide
W. Breitung, S. A. Wright
Nuclear Science and Engineering | Volume 105 | Number 4 | August 1990 | Pages 303-318
Technical Paper | doi.org/10.13182/NSE90-A21467
Neutron and Gamma-Ray Spectra from a Variety of Materials Bombarded with 14-MeV Neutrons
E. Goldberg, L. F. Hansen, T. T. Komoto, B. A. Pohl, R. J. Howerton, R. E. Dye, E. F. Plechaty, W. E. Warren
Nuclear Science and Engineering | Volume 105 | Number 4 | August 1990 | Pages 319-340
Technical Paper | doi.org/10.13182/NSE90-A21468
Determination of the Optical Constants of Liquid UO2 in the Near Infrared at 1064 nm
M. Bober, J. Singer
Nuclear Science and Engineering | Volume 105 | Number 4 | August 1990 | Pages 341-348
Technical Paper | doi.org/10.13182/NSE90-A21469
Multipoint Schemes for the Solution of the Diffusion Equation by Vectorial Computation
J. M. Martínez-Val, M. Piera, Y. Ronen
Nuclear Science and Engineering | Volume 105 | Number 4 | August 1990 | Pages 349-370
Technical Paper | doi.org/10.13182/NSE90-A21470
Optimized Automatic Reload Program for Pressurized Water Reactors Using Simple Direct Optimization Techniques
Joong Seok Suh, Samuel H. Levine
Nuclear Science and Engineering | Volume 105 | Number 4 | August 1990 | Pages 371-382
Technical Paper | doi.org/10.13182/NSE90-A21471
Sequential Probability Ratio Tests for Reactor Signal Validation and Sensor Surveillance Applications
Keith Humenik, Kenny C. Gross
Nuclear Science and Engineering | Volume 105 | Number 4 | August 1990 | Pages 383-390
Technical Paper | doi.org/10.13182/NSE90-A21472
Convective Heat Transfer in a Sealed Vertical Storage Cask Containing Spent-Fuel Canisters
M. Satishchandra Arya, M. Keyhani
Nuclear Science and Engineering | Volume 105 | Number 4 | August 1990 | Pages 391-403
Technical Paper | doi.org/10.13182/NSE90-A21473
Diagonally Dominant Enhancement Methods for Matrix Solvers in RELAP5
Arthur Shieh, Richard Riemke
Nuclear Science and Engineering | Volume 105 | Number 4 | August 1990 | Pages 404-408
Technical Paper | doi.org/10.13182/NSE90-A21474
