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Robotics & Remote Systems
The Mission of the Robotics and Remote Systems Division is to promote the development and application of immersive simulation, robotics, and remote systems for hazardous environments for the purpose of reducing hazardous exposure to individuals, reducing environmental hazards and reducing the cost of performing work.
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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
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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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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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Laboratory Measurement of the Heat Capacity of Urania up to 8000 K: I. Experiment
C. Ronchi, J. P. Hiernaut, R. Selfslag, G. J. Hyland
Nuclear Science and Engineering | Volume 113 | Number 1 | January 1993 | Pages 1-19
Technical Paper | doi.org/10.13182/NSE93-A23990
Heavy Nucleus Resonant Absorption Calculation Benchmarks
H. Tellier, M. Coste, C. Raepsaet, C. Van der Gucht
Nuclear Science and Engineering | Volume 113 | Number 1 | January 1993 | Pages 20-30
Technical Paper | doi.org/10.13182/NSE93-A23991
Langevin Equation Approach to Reactor Noise Analysis: Stochastic Transport Equation
A. Ziya Akcasu, Alison M. Stolle
Nuclear Science and Engineering | Volume 113 | Number 1 | January 1993 | Pages 31-55
Technical Paper | doi.org/10.13182/NSE93-A23992
A Stochastic Cellular Automata Model for Neutron Transport
Michael J. Gaeta, Bahram Nassersharif
Nuclear Science and Engineering | Volume 113 | Number 1 | January 1993 | Pages 56-69
Technical Paper | doi.org/10.13182/NSE93-A23993
Pressurized Water Reactor Core Parameter Prediction Using an Artificial Neural Network
Han Gon Kim, Soon Heung Chang, Byung Ho Lee
Nuclear Science and Engineering | Volume 113 | Number 1 | January 1993 | Pages 70-76
Technical Paper | doi.org/10.13182/NSE93-A23994
A Test of MCNP with a 6Li-Glass Moderating Neutron Detector
J. C. Wang, Gary L. Jensen, J. B. Czirr
Nuclear Science and Engineering | Volume 113 | Number 1 | January 1993 | Pages 77-85
Technical Paper | doi.org/10.13182/NSE93-A23995
Multigroup Antiproton Transport and Fission
B. R. Wienke, R. E. Seamon, D. G. Madland
Nuclear Science and Engineering | Volume 113 | Number 1 | January 1993 | Pages 86-92
Technical Note | doi.org/10.13182/NSE93-A23996
Neutronic Decoupling and Space-Dependent Nuclear Characteristics for Large Liquid-Metal Fast Breeder Reactor Cores
Toshio Sanda, Fumiaki Nakashima, Keisho Shirakata
Nuclear Science and Engineering | Volume 113 | Number 2 | February 1993 | Pages 97-108
Technical Paper | doi.org/10.13182/NSE113-97
Study of Compact Fast Reactor Core Designs
Tehsin Hamid, K. O. Ott
Nuclear Science and Engineering | Volume 113 | Number 2 | February 1993 | Pages 109-121
Technical Paper | doi.org/10.13182/NSE93-A24001
A Fast Reactor Transient Analysis Methodology for Personal Computers
K. O. Ott
Nuclear Science and Engineering | Volume 113 | Number 2 | February 1993 | Pages 122-135
Technical Paper | doi.org/10.13182/NSE93-A24002
Path Length Differencing and Energy Conservation of the SN Boltzmann/Spencer-Lewis Equation
W. L. Filippone, S. P. Monahan
Nuclear Science and Engineering | Volume 113 | Number 2 | February 1993 | Pages 136-144
Technical Paper | doi.org/10.13182/NSE93-A24003
Reactor Noise Analysis Based on Nonlinear Dynamic Theory — Application to Power Oscillation
Tomoaki Suzudo
Nuclear Science and Engineering | Volume 113 | Number 2 | February 1993 | Pages 145-160
Technical Paper | doi.org/10.13182/NSE93-A24004
Two Rossi-α Techniques for Measuring the Effective Delayed Neutron Fraction
Gregory D. Spriggs
Nuclear Science and Engineering | Volume 113 | Number 2 | February 1993 | Pages 161-172
Technical Paper | doi.org/10.13182/NSE93-2
Analysis of Tritium Production in a Sphere of 6LiD with Oralloy Core Irradiated by 14-MeV Neutrons
L. R. Fawcett, Jr.
Nuclear Science and Engineering | Volume 113 | Number 2 | February 1993 | Pages 173-183
Technical Paper | doi.org/10.13182/NSE93-A24006
Neutron Production in Heavy-lon Reactions at 35 and 50 MeV/Nucleon
H. R. Schelin, A. Galonsky, C. K. Gelbke, H. Hama, L. Heilbronn, D. Krofcheck, W. G. Lynch, D. Sackett, M. B. Tsang, X. Yang, F. Deák, Á. Horvath, Á. Kiss, Z. Seres, J. Kasagi, T. Murakami
Nuclear Science and Engineering | Volume 113 | Number 2 | February 1993 | Pages 184-188
Technical Paper | doi.org/10.13182/NSE93-A24007
Transient Gas Motion in Nuclear-Reactor-Pumped Lasers: Computational and Experimental Results
J. R. Torczynski, D.R. Neal
Nuclear Science and Engineering | Volume 113 | Number 3 | March 1993 | Pages 189-206
Technical Paper | doi.org/10.13182/NSE93-A24488
Solubility of Nickel and Cobalt Oxides in High-Temperature Water
Kostadin Dinov, Chihiro Matsuura, Daisuke Hiroishi, Kenkichi Ishigure
Nuclear Science and Engineering | Volume 113 | Number 3 | March 1993 | Pages 207-216
Technical Paper | doi.org/10.13182/NSE92-36
Thermal and Epithermal Sensitivities of Cobalt Self-Powered Neutron Detectors
Maria do Carmo Lopes, Jorge Molina Avila
Nuclear Science and Engineering | Volume 113 | Number 3 | March 1993 | Pages 217-226
Technical Paper | doi.org/10.13182/NSE93-A24490
A Consistent Technique for the Pin-by-Pin Homogenization of a Pressurized Water Reactor Assembly
A. Hébert
Nuclear Science and Engineering | Volume 113 | Number 3 | March 1993 | Pages 227-238
Technical Paper | doi.org/10.13182/NSE92-10
Criticality Analysis of Heterogeneous Light Water Reactor Configurations
S. Sitaraman, F. Rahnema
Nuclear Science and Engineering | Volume 113 | Number 3 | March 1993 | Pages 239-250
Technical Paper | doi.org/10.13182/NSE93-A24492
Stability Analysis of a Linear Reactor System with Feedback Under Low-Flow, Low-Power Conditions
E. V. Depiante
Nuclear Science and Engineering | Volume 113 | Number 3 | March 1993 | Pages 251-263
Technical Paper | doi.org/10.13182/NSE93-A24493
An Efficient Computational Technique for Thermal Reactor Transients
B. O. Cho, A. H. Robinson
Nuclear Science and Engineering | Volume 113 | Number 3 | March 1993 | Pages 264-270
Technical Paper | doi.org/10.13182/NSE93-A24494
Application of Galerkin’s Method to Calculate the Behavior of Boiling Water Reactors During Limit-Cycle Oscillations
B.Damiano,J. A. March-Leuba
Nuclear Science and Engineering | Volume 113 | Number 3 | March 1993 | Pages 271-281
Technical Note | doi.org/10.13182/NSE93-A24495
A Practical Algorithm to Derive the (α,n) Source Term in a Composite Mixture Containing Actinides
Ian R. Terry
Nuclear Science and Engineering | Volume 113 | Number 3 | March 1993 | Pages 282-285
Technical Note | doi.org/10.13182/NSE93-A24496
Thermohydraulic Behavior of the Liquid-Metal Natural-Circulation Target of the Spallation Neutron Source at Paul Scherrer Institute
Y. Takeda, W. E. Fischer
Nuclear Science and Engineering | Volume 113 | Number 4 | April 1993 | Pages 287-299
Technical Paper | doi.org/10.13182/NSE93-A15329
Suppression of Vapor Explosions by Dilute Aqueous Polymer Solutions
M. F. Dowling, B. M. Ip, S. I. Abdel-Khalik
Nuclear Science and Engineering | Volume 113 | Number 4 | April 1993 | Pages 300-313
Technical Paper | doi.org/10.13182/NSE93-A15330
Creating and Using a Type of Free-Form Geometry in Monte Carlo Particle Transport
Daniel E. Wessol, Floyd J. Wheeler
Nuclear Science and Engineering | Volume 113 | Number 4 | April 1993 | Pages 314-323
Technical Paper | doi.org/10.13182/NSE93-A15331
Quantifying the Reliability of Uncertainty Predictions in Monte Carlo Fast Reactor Physics Calculations
L. L. Carter, T. L. Miles, S. E. Binney
Nuclear Science and Engineering | Volume 113 | Number 4 | April 1993 | Pages 324-338
Technical Paper | doi.org/10.13182/NSE93-A15332
A New Approach and Computational Algorithm for Sensitivity/Uncertainty Analysis for SED and SAD with Application to Beryllium Integral Experiments
Peter M. Song, Mahmoud Z. Youssef, Mohamed A. Abdou
Nuclear Science and Engineering | Volume 113 | Number 4 | April 1993 | Pages 339-366
Technical Paper | doi.org/10.13182/NSE93-A15333
Detailed Behavior of Exposure Buildup Factor in Stratified Shields for Plane-Normal and Point Isotropic Sources, Including the Effects of Bremsstrahlung and Fluorescent Radiation
Yoshiko Harima, Hideo Hirayama
Nuclear Science and Engineering | Volume 113 | Number 4 | April 1993 | Pages 367-378
Technical Paper | doi.org/10.13182/NSE92-52
