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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.
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Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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!
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Latest News
Vogtle-3 shuts down for valve issue
One of the new Vogtle units in Georgia was shut down unexpectedly on Monday last week for a valve issue that has since been investigated and repaired. According to multiple local news outlets, Georgia Power reported on July 17 that Unit 3 was back in service.
Southern Company spokesperson Jacob Hawkins confirmed that Vogtle-3 went off line at 9:25 p.m. local time on July 8 “due to lowering water levels in the steam generators caused by a valve issue on one of the three main feedwater pumps.”
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Evaluation of Working Fluids in an Indirect Combined Cycle in a Very High Temperature Gas-Cooled Reactor
Chang H. Oh, Robert Barner, Cliff Davis, Steven Sherman
Nuclear Technology | Volume 156 | Number 1 | October 2006 | Pages 1-10
Technical Paper | Fission Reactors | doi.org/10.13182/NT06-A3769
Radiochemistry of Iodine: Outcomes of the CAIMAN Program
L. Cantrel
Nuclear Technology | Volume 156 | Number 1 | October 2006 | Pages 11-28
Technical Paper | Reactor Safety | doi.org/10.13182/NT156-11
Direct Simulation Monte Carlo Aerosol Dynamics: Coagulation and Collisional Sampling
Geethpriya Palaniswaamy, Sudarshan K. Loyalka
Nuclear Technology | Volume 156 | Number 1 | October 2006 | Pages 29-38
Technical Paper | Reactor Safety | doi.org/10.13182/NT06-A3771
Development and Verifications of Fast Reactor Fuel Design Code CEPTAR
T. Ozawa, T. Abe
Nuclear Technology | Volume 156 | Number 1 | October 2006 | Pages 39-55
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT156-39
Investigation of the Downcomer Boiling Phenomena During the Reflood Phase of a Postulated Large-Break LOCA in the APR1400
Byong-Jo Yun, Dong-Jin Euh, Chul-Hwa Song
Nuclear Technology | Volume 156 | Number 1 | October 2006 | Pages 56-68
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT06-A3773
Validation of COBRA-TF Critical Heat Flux Predictions for a Small-Hydraulic-Diameter Geometry Under Natural Boiling Conditions
Sule Ergun, Jason G. Williams, Lawrence E. Hochreiter, Hergen Wiersema, Marcel Slootman, Marek Stempniewicz
Nuclear Technology | Volume 156 | Number 1 | October 2006 | Pages 69-74
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT06-A3774
Treatment of Nuclear Data for Transport Problems Containing Detailed Temperature Distributions
T. H. Trumbull
Nuclear Technology | Volume 156 | Number 1 | October 2006 | Pages 75-86
Technical Paper | Radiation Protection | doi.org/10.13182/NT156-75
Caustic Precipitation of Plutonium and Uranium with Gadolinium as a Neutron Poison
Ann E. Visser, Michael G. Bronikowski, Tracy S. Rudisill
Nuclear Technology | Volume 156 | Number 1 | October 2006 | Pages 87-98
Technical Paper | Reprocessing | doi.org/10.13182/NT06-A3776
A Subcritical, Helium-Cooled Fast Reactor for the Transmutation of Spent Nuclear Fuel
W. M. Stacey, Z. Abbasi, C. J. Boyd, A. H. Bridges, E. A. Burgett, M. W. Cymbor, S. W. Fowler, A. T. Jones, R. S. Kelm, B. J. Kern, D. B. Lassiter, J. A. Maddox, W. B. Murphy, H. Park, J. M. Pounders, J. R. Preston
Nuclear Technology | Volume 156 | Number 1 | October 2006 | Pages 99-123
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT06-A3777
Developing a Tool for Simulating the Behavior of Axial Flux Difference During Power Reduction for Maanshan Pressurized Water Reactor Units
Jau-Tyne Yeh, Ta-Lun Sung, J. Y. Shiue
Nuclear Technology | Volume 156 | Number 2 | November 2006 | Pages 125-132
Technical Paper | Fission Reactors | doi.org/10.13182/NT06-A3778
Simulation of a PWR Reactor Vessel Level Indicating System During Station Blackout with MELCOR 1.8.5
Te-Chuan Wang, Shih-Jen Wang, Jyh-Tong Teng
Nuclear Technology | Volume 156 | Number 2 | November 2006 | Pages 133-139
Technical Paper | Fission Reactors | doi.org/10.13182/NT06-A3779
Off-Gas Source Estimation for Boiling Water Reactors Under Various Operation Conditions
Masato Takahashi
Nuclear Technology | Volume 156 | Number 2 | November 2006 | Pages 140-149
Technical Paper | Fission Reactors | doi.org/10.13182/NT06-A3780
Failure Mode and Effect Analysis Application for the Safety and Reliability Analysis of a Thermal-Hydraulic Passive System
Luciano Burgazzi
Nuclear Technology | Volume 156 | Number 2 | November 2006 | Pages 150-158
Technical Paper | Reactor Safety | doi.org/10.13182/NT06-A3781
Enhancement of Safety Analysis Capability for a CANDU-6 Reactor Using RELAP-CANDU/SCAN Coupled Code System
Manwoong Kim, Hyun-Koon Kim, Hho-Jung Kim, Su Hyon Hwang, In Seob Hong, Chang Hyo Kim
Nuclear Technology | Volume 156 | Number 2 | November 2006 | Pages 159-167
Technical Paper | Reactor Safety | doi.org/10.13182/NT06-A3782
Genetic Algorithm to Optimize the UO2/Gd2O3 Fuel Pin Designs in a Pressurized Water Reactor
Serkan Yilmaz, Kostadin Ivanov, Samuel Levine, Moussa Mahgerefteh
Nuclear Technology | Volume 156 | Number 2 | November 2006 | Pages 168-179
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT06-A3783
Genetic Algorithm Application for Burnable Poison Placement in PWRs with Optimized UO2/Gd2O3 Fuel Pin Configurations
Nuclear Technology | Volume 156 | Number 2 | November 2006 | Pages 180-190
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT06-A3784
Assessment of S/R5/MOD3.3 Models of Stratified Molten Pool and Debris-to-Vessel Contact Resistance by TMI-2 Lower-Head Creep Rupture Analyses
Sang Lung Chan
Nuclear Technology | Volume 156 | Number 2 | November 2006 | Pages 191-212
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT06-A3785
Properties of Titanium-Nitride for High-Level Waste Packaging Enhancement
C. C. Scheffing, K. Jagannadham, M.-S. Yim, M. A. Bourham, J. C. Farmer, J. J. Haslam, S. D. Day, D. V. Fix, N. Y. Yang
Nuclear Technology | Volume 156 | Number 2 | November 2006 | Pages 213-221
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT156-213
Numerical Study of Nuclide Migration in a Nonuniform Horizontal Flow Field of a High-Level Radioactive Waste Repository with Multiple Canisters
Doo-Hyun Lim
Nuclear Technology | Volume 156 | Number 2 | November 2006 | Pages 222-245
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT06-A3787
Assessment of a MOX Fuel Assembly Design for a BWR Mixed Reload
J. Ramon Ramirez, Gustavo Alonso, Robert T. Perry, Javier Ortiz-Villafuerte
Nuclear Technology | Volume 156 | Number 3 | December 2006 | Pages 247-255
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT06-A3788
Simulation Capability of the ATLAS Facility for Major Design-Basis Accidents
Ki Yong Choi, Hyun Sik Park, Dong Jin Euh, Tae Soon Kwon, Won Pil Baek
Nuclear Technology | Volume 156 | Number 3 | December 2006 | Pages 256-269
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT06-A3789
Detailed Analysis of Late-Phase Core-Melt Progression for the Evaluation of In-Vessel Corium Retention
R. J. Park, S. B. Kim, K. Y. Suh, J. L. Rempe, F. B. Cheung
Nuclear Technology | Volume 156 | Number 3 | December 2006 | Pages 270-281
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT06-A3790
Microgravity Phase Separation for the Rankine Cycle
Melissa Ghrist, Mike Ellis, David Bean, Cable Kurwitz, Frederick Best
Nuclear Technology | Volume 156 | Number 3 | December 2006 | Pages 282-288
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT06-A3791
A New Approach to Treating the Cell Property Averaging for a System Heat Transfer Analysis
Yoon Sub Sim
Nuclear Technology | Volume 156 | Number 3 | December 2006 | Pages 289-302
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT06-A3792
Linear Programming Approach for Optimization of Radionuclide Loading in Vitrified HLW
Joonhong Ahn, Myeongguk Cheon
Nuclear Technology | Volume 156 | Number 3 | December 2006 | Pages 303-319
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT06-A3793
Thermocouples for High-Temperature In-Pile Testing
J. L. Rempe, D. L. Knudson, K. G. Condie, S. Curtis Wilkins
Nuclear Technology | Volume 156 | Number 3 | December 2006 | Pages 320-331
Technical Paper | Radiation Measurements and Instrumentation | doi.org/10.13182/NT06-A3794
Review of Literature on Ruthenium Behavior in Nuclear Power Plant Severe Accidents
C. Mun, L. Cantrel, C. Madic
Nuclear Technology | Volume 156 | Number 3 | December 2006 | Pages 332-346
Technical Note | Reactor Safety | doi.org/10.13182/NT156-332
Effectiveness of the Raw-Water System as a Severe-Accident-Management Measure in Station Blackout Accidents
Nuclear Technology | Volume 156 | Number 3 | December 2006 | Pages 347-359
Technical Note | Thermal Hydraulics | doi.org/10.13182/NT06-A3796
Improvement of the Subchannel Flow Mixing Model of the MARS Code
Jae Jun Jeong, Dae Hyun Hwang, Bub Dong Chung
Nuclear Technology | Volume 156 | Number 3 | December 2006 | Pages 360-368
Technical Note | Thermal Hydraulics | doi.org/10.13182/NT06-A3797