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
Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
May 2025
Nuclear Technology
April 2025
Fusion Science and Technology
Latest News
X-energy, Dow apply to build an advanced reactor project in Texas
Dow and X-energy announced today that they have submitted a construction permit application to the Nuclear Regulatory Commission for a proposed advanced nuclear project in Seadrift, Texas. The project could begin construction later this decade, but only if Dow confirms “the ability to deliver the project while achieving its financial return targets.”
Jump to:
A Stylized Three-Dimensional Pressurized Water Reactor Benchmark Problem with UO2 and MOX Fuel
Farzad Rahnema, Ryan Hon, Steven Douglass
Nuclear Technology | Volume 184 | Number 1 | October 2013 | Pages 1-28
Technical Paper | Reactor Physics / Pressurized Water Reactors | doi.org/10.13182/NT11-124
Three-Dimensional Particle Transport Using Green's Functions in TRIPOLI-4 Monte Carlo Code: Application to PWR Neutron Fluence and Ex-Core Response Studies
S. Bourganel, O. Petit, C. M. Diop
Nuclear Technology | Volume 184 | Number 1 | October 2013 | Pages 29-41
Technical Paper | Neutron Transport and Shielding | doi.org/10.13182/NT13-A19866
Improved Irradiation Performance of Uranium-Molybdenum/Aluminum Dispersion Fuel by Silicon Addition in Aluminum
Yeon Soo Kim, G. L. Hofman, A. B. Robinson, D. M. Wachs
Nuclear Technology | Volume 184 | Number 1 | October 2013 | Pages 42-53
Technical Paper | Fuel Design/Defects/Examination / Fuel Performance/Bu/Isotopes | doi.org/10.13182/NT13-A19867
Rod-Inserted Sintering of Annular Pellets for Dual-Cooled Annular Fuel
Young Woo Rhee, Dong Joo Kim, Jong Hun Kim, Jae Ho Yang, Keon Sik Kim
Nuclear Technology | Volume 184 | Number 1 | October 2013 | Pages 54-62
Technical Paper | Fuel Design/Defects/Examination / Fuel Performance/Bu/Isotopes | doi.org/10.13182/NT13-A19868
Development and Application of an Integrated Fuel Performance and Subchannel Model for Analysis of Sodium Fast Reactors
J. W. Fricano, J. Buongiorno
Nuclear Technology | Volume 184 | Number 1 | October 2013 | Pages 63-77
Technical Paper | Fuel Design/Defects/Examination / Materials for Nuclear Fuels | doi.org/10.13182/NT13-A19869
Evolution of Charged Aerosols: Role of Charge on Coagulation
John F. Palsmeier, Sudarshan K. Loyalka
Nuclear Technology | Volume 184 | Number 1 | October 2013 | Pages 78-95
Technical Paper | Source Term Assessment | doi.org/10.13182/NT184-78
Method for Analyzing Fission Gas Release in Fuel Rods Based on Gamma-Ray Measurements of Short-Lived Fission Products
Scott Holcombe, Staffan Jacobsson Svärd, Knut Eitrheim, Lars Hallstadius, Christofer Willman
Nuclear Technology | Volume 184 | Number 1 | October 2013 | Pages 96-106
Technical Paper | Source Term Assessment / Techniques for Measurements of Nuclear Data / Nondestructive Examination/Testing Methods | doi.org/10.13182/NT13-A19871
Performance of Pyroprocess Equipment of Semi-Industrial Design and Material Balance in Repeated Engineering-Scale Fuel Cycle Tests Using Simulated Oxide/Metal Fuels
Masatoshi Iizuka, Kensuke Kinoshita, Yoshiharu Sakamura, Takanari Ogata, Tadafumi Koyama
Nuclear Technology | Volume 184 | Number 1 | October 2013 | Pages 107-120
Technical Paper | Pyrometallurgical Reprocessing | doi.org/10.13182/NT13-A19872
Resource Requirements and Proliferation Risks Associated with Small Modular Reactors
Alexander Glaser, Laura Berzak Hopkins, M. V. Ramana
Nuclear Technology | Volume 184 | Number 1 | October 2013 | Pages 121-129
Technical Paper | Proliferation Issues/Nuclear Safeguards | doi.org/10.13182/NT13-A19873
Monte Carlo and Deterministic Neutronics Analyses of YALINA Thermal Facility and Comparison with Experimental Results
Alberto Talamo, Yousry Gohar, H. Kiyavitskaya, V. Bournos, Y. Fokov, C. Routkovskaya
Nuclear Technology | Volume 184 | Number 2 | November 2013 | Pages 131-147
Technical Paper | Fission Reactors | doi.org/10.13182/NT13-A22310
Effective Reduction of Shutdown Dose Rate at Kuosheng Boiling Water Reactors Operating Under Hydrogen Water Chemistry
Tsung-Kuang Yeh, Mei-Ya Wang, Robin Wu
Nuclear Technology | Volume 184 | Number 2 | November 2013 | Pages 148-155
Technical Paper | Fission Reactors | doi.org/10.13182/NT13-A22311
Parametric Core Analysis and Economic Feasibility of a Thorium Heavy Water Breeder Reactor
Taraknath Woddi, Kenneth N. Ricci
Nuclear Technology | Volume 184 | Number 2 | November 2013 | Pages 156-168
Technical Paper | Fission Reactors | doi.org/10.13182/NT13-22
The Energy Multiplier Module: Advancing the Nuclear Fuel Cycle Through Technology Innovations
R. W. Schleicher, H. Choi, J. Rawls
Nuclear Technology | Volume 184 | Number 2 | November 2013 | Pages 169-180
Technical Paper | Fission Reactors | doi.org/10.13182/NT13-A22313
Representative Source Terms and the Influence of Reactor Attributes on Functional Containment in Modular High-Temperature Gas-Cooled Reactors
D. A. Petti, R. R. Hobbins, P. Lowry, H. Gougar
Nuclear Technology | Volume 184 | Number 2 | November 2013 | Pages 181-197
Technical Paper | Fission Reactors | doi.org/10.13182/NT184-181
Design, Construction, and Demonstration of the Colorado School of Mines Neutron Imaging Facility
Aaron E. Craft, Jeffrey C. King
Nuclear Technology | Volume 184 | Number 2 | November 2013 | Pages 198-209
Technical Paper | Fission Reactors | doi.org/10.13182/NT13-A22315
The Consequences of a Sharp Temperature Change in the Fuel Pins of an Accelerator-Driven Subcritical System
R. Dagan, A. Jianu, G. Rimpault, A. Weisenburger, M. Schikorr
Nuclear Technology | Volume 184 | Number 2 | November 2013 | Pages 210-216
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT13-A22316
Experimental Validation of the DARWIN2.3 Package for Fuel Cycle Applications
L. San-Felice, R. Eschbach, P. Bourdot
Nuclear Technology | Volume 184 | Number 2 | November 2013 | Pages 217-232
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT12-121
Optimized Design of a PGNAA System for Cement Analysis Using Monte Carlo Simulations
J. B. Yang, X. G. Tuo, Z. Li, Y. Cheng, L. Wang, H. H. Wang, B. Cai, M. Z. Liu
Nuclear Technology | Volume 184 | Number 2 | November 2013 | Pages 233-238
Technical Paper | Radiation Transport and Protection | doi.org/10.13182/NT13-A22318
A Notable Comparison of Computational Geometries in MCNP6 Calculations
Roger L. Martz, Kevin M. Marshall
Nuclear Technology | Volume 184 | Number 2 | November 2013 | Pages 239-248
Technical Paper | Radiation Transport and Protection | doi.org/10.13182/NT13-A22319
The Issue of Accelerator Beam Trips for Efficient ADS Operation
G. Rimpault, Ph. Darde, F. Mellier, R. Dagan, M. Schikorr, A. Weisenburger, D. Maes, V. Sobolev, B. Arien, D. Lamberts, D. De Bruyn, A. C. Mueller, J. L. Biarrotte
Nuclear Technology | Volume 184 | Number 2 | November 2013 | Pages 249-260
Technical Paper | Accelerators | doi.org/10.13182/NT12-75
BWR-HD: An Optimized Boiling Water Reactor with High Power Density
Koroush Shirvan, Mujid Kazimi
Nuclear Technology | Volume 184 | Number 3 | December 2013 | Pages 261-273
Technical Paper | Fission Reactors | doi.org/10.13182/NT13-A24984
Safety Analysis of BWR-HD: An Optimized Boiling Water Reactor with High Power Density
Nuclear Technology | Volume 184 | Number 3 | December 2013 | Pages 274-286
Technical Paper | Fission Reactors | doi.org/10.13182/NT13-A24985
Stability Analysis of BWR-HD: An Optimized Boiling Water Reactor with High Power Density
Nuclear Technology | Volume 184 | Number 3 | December 2013 | Pages 287-296
Technical Paper | Fission Reactors | doi.org/10.13182/NT13-A24986
Design of SPLC Architecture Used in Advanced Nuclear Safety System and Reliability Analysis Using Markov Model
Gwang Seop Son, Dong Hoon Kim, Choul Woong Son, Joon Kyo Kim, Jae Hyun Park
Nuclear Technology | Volume 184 | Number 3 | December 2013 | Pages 297-309
Technical Paper | Reactor Safety | doi.org/10.13182/NT13-A24987
Operating Manipulator Arm by Robot Suit HAL for Remote In-Cell Equipment Maintenance
Akihiro Kitamura, Takashi Namekawa, Kousuke Hiramatsu, Yoshiyuki Sankai
Nuclear Technology | Volume 184 | Number 3 | December 2013 | Pages 310-319
Technical Paper | Robotic and Remote Systems / Human Factors | doi.org/10.13182/NT13-A24988
Assessment of the Fingerprinting Method for the Verification of Spent Fuel in MACSTOR KN-400 CANDU Spent-Fuel Dry Storage
Nandan G. Chandregowda, Sunil S. Chirayath, William S. Charlton, Young Ham, Shiva Sitaraman, Gil Hoon Ahn
Nuclear Technology | Volume 184 | Number 3 | December 2013 | Pages 320-332
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT13-A24989
Uncertainty and Sensitivity Study in the Frame of TRACE Validation for Reflood Experiment
Wadim Jaeger, Victor Hugo Sanchez Espinoza
Nuclear Technology | Volume 184 | Number 3 | December 2013 | Pages 333-350
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT184-333
Quest for a Material for Sulfuric Acid Superheater/Decomposer for Sulfur-Iodine Thermochemical Cycle for Hydrogen Production
Michael S. Peck, Tushar K. Ghosh, Mark A. Prelas
Nuclear Technology | Volume 184 | Number 3 | December 2013 | Pages 351-363
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT13-A24991
