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
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
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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
Dec 2024
Jul 2024
Latest Journal Issues
Nuclear Science and Engineering
December 2024
Nuclear Technology
Fusion Science and Technology
November 2024
Latest News
ANS standard updated for determining meteorological information at nuclear facilities
Following approval in October from the American National Standards Institute, ANSI/ANS-3.11-2024, Determining Meteorological Information at Nuclear Facilities, was published in late November. This standard provides criteria for gathering, assembling, processing, storing, and disseminating meteorological information at commercial nuclear power plants, U.S. Department of Energy/National Nuclear Security Administration nuclear facilities, and other national or international nuclear facilities.
Jump to:
Determination of the 232Th(n,) Cross Section from 4 to 140 keV at GELINA
A. Borella, K. Volev, A. Brusegan, P. Schillebeeckx, F. Corvi, N. Koyumdjieva, N. Janeva, A. A. Lukyanov
Nuclear Science and Engineering | Volume 152 | Number 1 | January 2006 | Pages 1-14
Technical Paper | doi.org/10.13182/NSE06-A2557
Comparison of Ramsauer and Optical Model Neutron Angular Distributions
D. P. McNabb, J. D. Anderson, R. W. Bauer, F. S. Dietrich, S. M. Grimes, C. A. Hagmann
Nuclear Science and Engineering | Volume 152 | Number 1 | January 2006 | Pages 15-22
Technical Paper | doi.org/10.13182/NSE06-A2558
Investigation of the Ramsauer Model for the Prediction of Neutron Cross Sections Below 120 MeV
R. S. Gowda, S. Ganesan
Nuclear Science and Engineering | Volume 152 | Number 1 | January 2006 | Pages 23-28
Technical Paper | doi.org/10.13182/NSE06-A2559
Generalization of the Variational Nodal Method to Spherical Harmonics Approximations in R-Z Geometry
Hui Zhang, E. E. Lewis
Nuclear Science and Engineering | Volume 152 | Number 1 | January 2006 | Pages 29-36
Technical Paper | doi.org/10.13182/NSE06-A2560
Development of Probabilistic Design Method for Fast Reactor Fuel Rod
T. Ozawa, T. Abe
Nuclear Science and Engineering | Volume 152 | Number 1 | January 2006 | Pages 37-47
Technical Paper | doi.org/10.13182/NSE06-A2561
A New Automatic Biasing Technique for Transport Monte Carlo Methods
Jean-Marc Depinay, Michel Caillaud, Remi Sentis
Nuclear Science and Engineering | Volume 152 | Number 1 | January 2006 | Pages 48-55
Technical Paper | doi.org/10.13182/NSE06-A2562
Implications of Monte Carlo Statistical Errors in Criticality Safety Assessments
Ronald E. Pevey
Nuclear Science and Engineering | Volume 152 | Number 1 | January 2006 | Pages 56-64
Technical Paper | doi.org/10.13182/NSE06-A2563
Results and Analysis of the Spherical 237Np Critical Experiment Surrounded by Highly Enriched Uranium Hemispherical Shells
David Loaiza, Rene Sanchez, David Hayes, Charlene Cappiello
Nuclear Science and Engineering | Volume 152 | Number 1 | January 2006 | Pages 65-75
Technical Paper | doi.org/10.13182/NSE06-A2564
A Device for Nondestructive Experimental Determination of the Power Distribution in a Nuclear Fuel Assembly
P. Jansson, S. Jacobsson Svärd, A. Håkansson, A. Bäcklin
Nuclear Science and Engineering | Volume 152 | Number 1 | January 2006 | Pages 76-86
Technical Paper | doi.org/10.13182/NSE06-A2565
GAMMA Multidimensional Multicomponent Mixture Analysis to Predict Air Ingress Phenomena in an HTGR
Hong Sik Lim, Hee Cheon No
Nuclear Science and Engineering | Volume 152 | Number 1 | January 2006 | Pages 87-97
Technical Paper | doi.org/10.13182/NSE06-5
Electromagnetic Excitation Rates for Nuclear Isomers in a Hot Dense Plasma
T. C. Luu, J. L. Friar, A. C. Hayes
Nuclear Science and Engineering | Volume 152 | Number 1 | January 2006 | Pages 98-105
Technical Paper | doi.org/10.13182/NSE06-A2567
Identification of an Unknown Material in a Radiation Shield Using the Schwinger Inverse Method
Jeffrey A. Favorite, Keith C. Bledsoe
Nuclear Science and Engineering | Volume 152 | Number 1 | January 2006 | Pages 106-117
Technical Note | doi.org/10.13182/NSE152-106
Improvement of Low-Pressure Subcooled Boiling Models in RELAP/MOD3.2 Code for Predicting Flow Instability
E. M. Dilla, J. Y. Tu, G. H. Yeoh
Nuclear Science and Engineering | Volume 152 | Number 1 | January 2006 | Pages 118-124
Technical Note | doi.org/10.13182/NSE06-A2569
Experimental Determination of the Decay Constants and Abundances of Delayed Neutrons by Means of Reactor Noise Analysis
Ricardo Diniz, Adimir dos Santos
Nuclear Science and Engineering | Volume 152 | Number 2 | February 2006 | Pages 125-141
Technical Paper | doi.org/10.13182/NSE04-69
Calculating the Effective Delayed Neutron Fraction with Monte Carlo
Robin Klein Meulekamp, Steven C. van der Marck
Nuclear Science and Engineering | Volume 152 | Number 2 | February 2006 | Pages 142-148
Technical Paper | doi.org/10.13182/NSE03-107
Mixed-Hybrid Transport Discretization Using Even and Odd PN Expansions
S. Van Criekingen, E. E. Lewis, R. Beauwens
Nuclear Science and Engineering | Volume 152 | Number 2 | February 2006 | Pages 149-163
Technical Paper | doi.org/10.13182/NSE06-1
A Diffusion Synthetic Acceleration Method for Block Adaptive Mesh Refinement
Robert C. Ward, Randal S. Baker, Jim E. Morel
Nuclear Science and Engineering | Volume 152 | Number 2 | February 2006 | Pages 164-179
Technical Paper | doi.org/10.13182/NSE06-A2573
Variational Estimates of Internal Interface Perturbations and a New Variational Functional for Inhomogeneous Transport Problems
Jeffrey A. Favorite
Nuclear Science and Engineering | Volume 152 | Number 2 | February 2006 | Pages 180-196
Technical Paper | doi.org/10.13182/NSE06-A2574
Particle Swarm Optimization in Reactor Core Design
Roberto P. Domingos, Roberto Schirru, Cláudio M. N. A. Pereira
Nuclear Science and Engineering | Volume 152 | Number 2 | February 2006 | Pages 197-203
Technical Paper | doi.org/10.13182/NSE06-A2575
A Physics Study of a 600-MW(thermal) Gas-Cooled Fast Reactor
Hangbok Choi, Gérald Rimpault, Jean C. Bosq
Nuclear Science and Engineering | Volume 152 | Number 2 | February 2006 | Pages 204-218
Technical Paper | doi.org/10.13182/NSE06-A2576
Analysis of a BWR Turbine Trip Experiment by Entire Plant Simulation with Spatial Kinetics
Yoshiro Asahi, Tomoaki Suzudo, Nobuyuki Ishikawa, Toru Nakatsuka
Nuclear Science and Engineering | Volume 152 | Number 2 | February 2006 | Pages 219-235
Technical Paper | doi.org/10.13182/NSE06-A2577
Excitation Behavior of Rare Gases in Low-Energy Plasma
Hiroaki Ogawa, Kiyoshi Kiuchi
Nuclear Science and Engineering | Volume 152 | Number 2 | February 2006 | Pages 236-241
Technical Paper | doi.org/10.13182/NSE06-A2578
Analog Monte Carlo Methods for Simulating Isotopic Inventories in Complex Systems
Paul Wilson, Phiphat Phruksarojanakun
Nuclear Science and Engineering | Volume 152 | Number 3 | March 2006 | Pages 243-255
Technical Paper | doi.org/10.13182/NSE06-A2579
Effect of Transverse Neutron Leakage on the Attenuation of the Displacements per Atom in the Reactor Pressure Vessel
John F. Carew, Kai Hu
Nuclear Science and Engineering | Volume 152 | Number 3 | March 2006 | Pages 256-273
Technical Paper | doi.org/10.13182/NSE06-A2580
Stochastic Approximation for Monte Carlo Calculation of Steady-State Conditions in Thermal Reactors
Jan Dufek, Waclaw Gudowski
Nuclear Science and Engineering | Volume 152 | Number 3 | March 2006 | Pages 274-283
Technical Paper | doi.org/10.13182/NSE06-2
Thermal Neutron Diffusion in an Array of Plates
B. D. Ganapol
Nuclear Science and Engineering | Volume 152 | Number 3 | March 2006 | Pages 284-291
Technical Paper | doi.org/10.13182/NSE06-A2582
Analysis of Single Rod Drop Transient in BWR Considering Detailed Intrabundle Void Distribution
Akitoshi Hotta, Hiroshi Shirai, Shinya Mizokami
Nuclear Science and Engineering | Volume 152 | Number 3 | March 2006 | Pages 292-305
Technical Paper | doi.org/10.13182/NSE06-A2583
Use of 240Pu Waste as a Burnable Absorber in Light Water Reactors
Edward P. Naessens, Jr., Kenneth S. Allen, Brian E. Moretti
Nuclear Science and Engineering | Volume 152 | Number 3 | March 2006 | Pages 306-313
Technical Paper | doi.org/10.13182/NSE06-A2584
Measurement of 16N Gamma Rays with Argon-Filled Three-Electrode Ionization Chamber as Reactor Power Level Indicator
Muhammad Munir, Nasir Ahmad
Nuclear Science and Engineering | Volume 152 | Number 3 | March 2006 | Pages 314-319
Technical Paper | doi.org/10.13182/NSE06-A2585
Determination of Intermediate Energy Neutron Cross Sections Using the Ramsauer Model
M. Azam, R. S. Gowda, S. Ganesan
Nuclear Science and Engineering | Volume 152 | Number 3 | March 2006 | Pages 320-324
Technical Paper | doi.org/10.13182/NSE06-A2586
Calculation and Evaluation of Neutron-Induced Reactions on 58Ni Below 150 MeV
Xiaolong Huang
Nuclear Science and Engineering | Volume 152 | Number 3 | March 2006 | Pages 325-333
Technical Note | doi.org/10.13182/NSE06-A2587
A Rule for Determining Fissile Isotopes
Yigal Ronen
Nuclear Science and Engineering | Volume 152 | Number 3 | March 2006 | Pages 334-335
Technical Note | doi.org/10.13182/NSE06-A2588
