ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
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
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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!
Latest Magazine Issues
Mar 2025
Jul 2024
Latest Journal Issues
Nuclear Science and Engineering
March 2025
Nuclear Technology
Fusion Science and Technology
February 2025
Latest News
ARG-US Remote Monitoring Systems: Use Cases and Applications in Nuclear Facilities and During Transportation
As highlighted in the Spring 2024 issue of Radwaste Solutions, researchers at the Department of Energy’s Argonne National Laboratory are developing and deploying ARG-US—meaning “Watchful Guardian”—remote monitoring systems technologies to enhance the safety, security, and safeguards (3S) of packages of nuclear and other radioactive material during storage, transportation, and disposal.
Jump to:
Development of a Method for Measuring the Moderator Temperature Coefficient by Noise Analysis and Its Experimental Verification in Ringhals-2
C. Demazière, I. Pázsit
Nuclear Science and Engineering | Volume 148 | Number 1 | September 2004 | Pages 1-29
Technical Paper | doi.org/10.13182/NSE04-A2437
Calculating Probability Tables for the Unresolved-Resonance Region Using Monte Carlo Methods
M. E. Dunn, L. C. Leal
Nuclear Science and Engineering | Volume 148 | Number 1 | September 2004 | Pages 30-42
Technical Paper | doi.org/10.13182/NSE04-A2438
Statistical Assignment of Neutron Orbital Angular Momentum to a Resonance
Soo-Youl Oh, Jonghwa Chang, Luiz C. Leal
Nuclear Science and Engineering | Volume 148 | Number 1 | September 2004 | Pages 43-49
Technical Paper | doi.org/10.13182/NSE04-A2439
An Interpretation of Energy Dependence of Delayed Neutron Yields in the Resonance Region for 235U and 239Pu
Takaaki Ohsawa, Franz-Josef Hambsch
Nuclear Science and Engineering | Volume 148 | Number 1 | September 2004 | Pages 50-54
Technical Paper | doi.org/10.13182/NSE04-A2440
On the Neutron Kinetics and Control of Accelerator-Driven Systems
D. G. Cacuci
Nuclear Science and Engineering | Volume 148 | Number 1 | September 2004 | Pages 55-66
Technical Paper | doi.org/10.13182/NSE148-55
Theory and Analysis of the Feynman-Alpha Method for Deterministically and Randomly Pulsed Neutron Sources
I. Pázsit, M. Ceder, Z. Kuang
Nuclear Science and Engineering | Volume 148 | Number 1 | September 2004 | Pages 67-78
Technical Paper | doi.org/10.13182/NSE04-A2442
Application of the Multipoint Method to the Kinetics of Accelerator-Driven Systems
P. Ravetto, M. M. Rostagno, G. Bianchini, M. Carta, A. D'Angelo
Nuclear Science and Engineering | Volume 148 | Number 1 | September 2004 | Pages 79-88
Technical Paper | doi.org/10.13182/NSE02-10D
Transport Effects for Source-Oscillated Problems in Subcritical Systems
S. Dulla, P. Ravetto, M. M. Rostagno
Nuclear Science and Engineering | Volume 148 | Number 1 | September 2004 | Pages 89-102
Technical Paper | doi.org/10.13182/NSE04-A2444
Neutronic Analyses of the Trade Demonstration Facility
C. Rubbia, M. Carta, N. Burgio, C. Ciavola, A. D'Angelo, A. Dodaro, A. Festinesi, S. Monti, A. Santagata, F. Troiani, M. Salvatores, M. Delpech, Y. Kadi, S. Buono, A. Ferrari, A. Herrera Martínez, L. Zanini, G. Imel
Nuclear Science and Engineering | Volume 148 | Number 1 | September 2004 | Pages 103-123
Technical Paper | doi.org/10.13182/NSE04-A2445
Neutronic Studies in Support of Accelerator-Driven Systems: The MUSE Experiments in the MASURCA Facility
R. Soule, W. Assal, P. Chaussonnet, C. Destouches, C. Domergue, C. Jammes, J.-M. Laurens, J.-F. Lebrat, F. Mellier, G. Perret, G. Rimpault, H. Servière, G. Imel, G. M. Thomas, D. Villamarin, E. Gonzalez-Romero, M. Plaschy, R. Chawla, J. L. Kloosterman, Y. Rugama, A. Billebaud, R. Brissot, D. Heuer, M. Kerveno, C. Le Brun, E. Liatard, J.-M. Loiseaux, O. Méplan, E. Merle, F. Perdu, J. Vollaire, P. Baeten
Nuclear Science and Engineering | Volume 148 | Number 1 | September 2004 | Pages 124-152
Technical Paper | doi.org/10.13182/NSE01-13C
A Receding Horizon Controller with a Parameter Estimator for Nuclear Reactor Power Distribution
Man Gyun Na, Dong Won Jung, Sun Mi Lee
Nuclear Science and Engineering | Volume 148 | Number 1 | September 2004 | Pages 153-161
Technical Paper | doi.org/10.13182/NSE04-A2447
Development and Application of a Decomposition Methodology for Interpretation of Reactivity Effect Discrepancies
R. van Geemert, F. Jatuff, F. Tani, R. Chawla
Nuclear Science and Engineering | Volume 148 | Number 1 | September 2004 | Pages 162-171
Technical Paper | doi.org/10.13182/NSE04-A2448
RTk/SN Solutions of the Two-Dimensional Multigroup Transport Equations in Hexagonal Geometry
Edmundo del Valle, Ernest H. Mund
Nuclear Science and Engineering | Volume 148 | Number 1 | September 2004 | Pages 172-185
Technical Paper | doi.org/10.13182/NSE04-A2449
A Second-Order Finite Volume Discretization of the Time-Dependent Transport Equation on Arbitrary Quadrilaterals in R-Z Geometry
Alexander V. Voronkov, Elena P. Sychugova
Nuclear Science and Engineering | Volume 148 | Number 1 | September 2004 | Pages 186-194
Technical Paper | doi.org/10.13182/NSE04-A2450
OECD/NRC BWR Turbine Trip Transient Benchmark as a Basis for Comprehensive Qualification and Studying Best-Estimate Coupled Codes
Kostadin Ivanov, Andy Olson, Enrico Sartori
Nuclear Science and Engineering | Volume 148 | Number 2 | October 2004 | Pages 195-207
Technical Paper | doi.org/10.13182/NSE04-A2451
Application of TRAC/BF1-ENTRÉE-NASCA to OECD NEA/NSC BWR Turbine Trip Benchmark
Akitoshi Hotta, Minyan Zhang, Hiroshi Shirai
Nuclear Science and Engineering | Volume 148 | Number 2 | October 2004 | Pages 208-225
Technical Paper | doi.org/10.13182/NSE04-A2452
Analysis of the Boiling Water Reactor Turbine Trip Benchmark with the Codes DYN3D and ATHLET/DYN3D
Ulrich Grundmann, Sören Kliem, Ulrich Rohde
Nuclear Science and Engineering | Volume 148 | Number 2 | October 2004 | Pages 226-234
Technical Paper | doi.org/10.13182/NSE04-A2453
Computation of a BWR Turbine Trip with CATHARE-CRONOS2-FLICA4 Coupled Codes
G. Mignot, E. Royer, B. Rameau, N. Todorova
Nuclear Science and Engineering | Volume 148 | Number 2 | October 2004 | Pages 235-246
Technical Paper | doi.org/10.13182/NSE04-A2454
OECD/NRC BWR Turbine Trip Benchmark: Simulation by POLCA-T Code
Dobromir Panayotov
Nuclear Science and Engineering | Volume 148 | Number 2 | October 2004 | Pages 247-255
Technical Paper | doi.org/10.13182/NSE04-A2455
Peach Bottom Transients Analysis with TRAC/BF1-VALKIN
G. Verdú, R. Miró, A. M. Sánchez, O. Roselló, D. Ginestar, V. Vidal
Nuclear Science and Engineering | Volume 148 | Number 2 | October 2004 | Pages 256-269
Technical Paper | doi.org/10.13182/NSE04-A2456
Analysis of the OECD/NRC BWR Turbine Trip Benchmark by the Coupled-Code System ATHLET-QUABOX/CUBBOX
S. Langenbuch, K.-D. Schmidt, K. Velkov
Nuclear Science and Engineering | Volume 148 | Number 2 | October 2004 | Pages 270-280
Technical Paper | doi.org/10.13182/NSE04-A2457
Peach Bottom 2 Turbine Trip Simulation Using TRAC-BF1/COS3D, a Best-Estimate Coupled 3-D Core and Thermal-Hydraulic Code System
Atsushi Ui, Takamasa Miyaji
Nuclear Science and Engineering | Volume 148 | Number 2 | October 2004 | Pages 281-290
Technical Paper | doi.org/10.13182/NSE04-A2458
Analysis of the OECD/NRC BWR Turbine Trip Transient Benchmark with the Coupled Thermal-Hydraulics and Neutronics Code TRAC-M/PARCS
Deokjung Lee, Thomas J. Downar, Anthony Ulses, Bedirhan Akdeniz, Kostadin N. Ivanov
Nuclear Science and Engineering | Volume 148 | Number 2 | October 2004 | Pages 291-305
Technical Paper | doi.org/10.13182/NSE04-A2459
Peach Bottom BWR Turbine Trip Benchmark Analyses with RETRAN-3D and CORETRAN
W. Barten, H. Ferroukhi, P. Coddington
Nuclear Science and Engineering | Volume 148 | Number 2 | October 2004 | Pages 306-324
Technical Paper | doi.org/10.13182/NSE04-A2460
SIMULATE-3K Peach Bottom 2 Turbine Trip 2 Benchmark Calculations
Lotfi A. Belblidia, Gerardo M. Grandi, Christian Jönsson
Nuclear Science and Engineering | Volume 148 | Number 2 | October 2004 | Pages 325-336
Technical Paper | doi.org/10.13182/NSE04-A2461
Analysis of the Peach Bottom Turbine Trip 2 Experiment by Coupled RELAP5-PARCS Three-Dimensional Codes
Anis Bousbia-Salah, Juswald Vedovi, Francesco D'Auria, Kostadin Ivanov, Giorgio Galassi
Nuclear Science and Engineering | Volume 148 | Number 2 | October 2004 | Pages 337-353
Technical Paper | doi.org/10.13182/NSE04-A2462
Coarse-Mesh Angular Dependent Rebalance Acceleration of the Discrete Ordinates Transport Calculations
Young Ryong Park, Nam Zin Cho
Nuclear Science and Engineering | Volume 148 | Number 3 | November 2004 | Pages 355-373
Technical Paper | doi.org/10.13182/NSE03-12
Time Series Analysis of Monte Carlo Fission Sources—I: Dominance Ratio Computation
Taro Ueki, Forrest B. Brown, D. Kent Parsons, James S. Warsa
Nuclear Science and Engineering | Volume 148 | Number 3 | November 2004 | Pages 374-390
Technical Paper | doi.org/10.13182/NSE03-95
Ex Post Facto Monte Carlo Variance Reduction
Thomas E. Booth
Nuclear Science and Engineering | Volume 148 | Number 3 | November 2004 | Pages 391-402
Technical Paper | doi.org/10.13182/NSE04-A2465
An Analytical Study of Particle Transport in Spatially Random Media in One Dimension: Mean and Variance Calculations
A. Z. Akcasu, M. M. R. Williams
Nuclear Science and Engineering | Volume 148 | Number 3 | November 2004 | Pages 403-413
Technical Paper | doi.org/10.13182/NSE04-A2466
Development of Pressurized Water Reactor Integrated Safety Analysis Methodology Using Multilevel Coupling Algorithm
Dmitri Ziabletsev, Maria Avramova, Kostadin Ivanov
Nuclear Science and Engineering | Volume 148 | Number 3 | November 2004 | Pages 414-425
Technical Paper | doi.org/10.13182/NSE04-A2467
Development of a Unique Curve for Thermal Neutron Self-Shielding Factor in Spherical Scattering Materials
J. Salgado, I. F. Gonçalves, E. Martinho
Nuclear Science and Engineering | Volume 148 | Number 3 | November 2004 | Pages 426-428
Technical Paper | doi.org/10.13182/NSE04-A2468
Time-Varying Characteristics Analysis and Fuzzy Controller Systematic Design Method for Pressurized Water Reactor Power Control
Shengzhi Liu, Naiyao Zhang, Zhenhua Cui
Nuclear Science and Engineering | Volume 148 | Number 3 | November 2004 | Pages 429-444
Technical Paper | doi.org/10.13182/NSE04-A2469
Collision Integral Cross Sections in Double Photon Compton Scattering and a Possible Method for Their Measurement
Aarti Sharma, M. B. Saddi, B. Singh, B. S. Sandhu
Nuclear Science and Engineering | Volume 148 | Number 3 | November 2004 | Pages 445-452
Technical Paper | doi.org/10.13182/NSE04-A2470
The Thermal Diffusion Length Problem in an Array of Plates
J. S. Cassell, M. M. R. Williams
Nuclear Science and Engineering | Volume 148 | Number 3 | November 2004 | Pages 453-457
Technical Note | doi.org/10.13182/NSE04-A2471
Resource Note on Photofission of Nuclei for 235U and 239Pu Detection
Michael Martin Nieto
Nuclear Science and Engineering | Volume 148 | Number 3 | November 2004 | Pages 458-461
Technical Note | doi.org/10.13182/NSE04-A2472
