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
Aerospace Nuclear Science & Technology
Organized to promote the advancement of knowledge in the use of nuclear science and technologies in the aerospace application. Specialized nuclear-based technologies and applications are needed to advance the state-of-the-art in aerospace design, engineering and operations to explore planetary bodies in our solar system and beyond, plus enhance the safety of air travel, especially high speed air travel. Areas of interest will include but are not limited to the creation of nuclear-based power and propulsion systems, multifunctional materials to protect humans and electronic components from atmospheric, space, and nuclear power system radiation, human factor strategies for the safety and reliable operation of nuclear power and propulsion plants by non-specialized personnel and more.
Meeting Spotlight
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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
Apr 2024
Jan 2024
Latest Journal Issues
Nuclear Science and Engineering
May 2024
Nuclear Technology
Fusion Science and Technology
Latest News
College students help develop waste-measuring device at Hanford
A partnership between Washington River Protection Solutions (WRPS) and Washington State University has resulted in the development of a device to measure radioactive and chemical tank waste at the Hanford Site. WRPS is the contractor at Hanford for the Department of Energy’s Office of Environmental Management.
Jump to:
Stability Monitoring Tests Using a Nuclear-Coupled Boiling Channel Model
Miguel Ceceñas-Falcón, Robert M. Edwards
Nuclear Technology | Volume 131 | Number 1 | July 2000 | Pages 1-11
Technical Paper | Reactor Safety | doi.org/10.13182/NT00-A3100
Theoretical Derivation of Simplified Evaluation Models for the First Peak of a Criticality Accident in Nuclear Fuel Solution
Yasushi Nomura
Nuclear Technology | Volume 131 | Number 1 | July 2000 | Pages 12-21
Technical Paper | Reactor Safety | doi.org/10.13182/NT00-A3101
Fission-Product Release During Transient Heating of Irradiated CANDU Fuel
Zhendong Liu, Raymond S. Dickson, Lawrence W. Dickson, Zoran Bilanovic, David S. Cox
Nuclear Technology | Volume 131 | Number 1 | July 2000 | Pages 22-35
Technical Paper | Reactor Safety | doi.org/10.13182/NT00-A3102
Fission Product Release Behavior of Individual Coated Fuel Particles for High-Temperature Gas-Cooled Reactors
Kazuo Minato, Kazuhiro Sawa, Toshio Koya, Takeshi Tomita, Akiyoshi Ishikawa, Charles A. Baldwin, William Alexander Gabbard, Charlie M. Malone
Nuclear Technology | Volume 131 | Number 1 | July 2000 | Pages 36-47
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT00-A3103
FORMOSA-B: A Boiling Water Reactor In-Core Fuel Management Optimization Package II
Atul A. Karve, Paul J. Turinsky
Nuclear Technology | Volume 131 | Number 1 | July 2000 | Pages 48-68
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT00-A3104
Application of the Two-Dimensional Navier-Stokes Equations to Steam Cooling in Asymmetrically Heated Channels
L. W. Ward
Nuclear Technology | Volume 131 | Number 1 | July 2000 | Pages 69-81
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT00-A3105
Analysis of PANDA Passive Containment Cooling Steady-State Tests with the Spectra Code
Marek M. Stempniewicz
Nuclear Technology | Volume 131 | Number 1 | July 2000 | Pages 82-101
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT00-A3106
Current State of Knowledge of Water Radiolysis Effects on Spent Nuclear Fuel Corrosion
H. Christensen, S. Sunder
Nuclear Technology | Volume 131 | Number 1 | July 2000 | Pages 102-123
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT00-A3107
Thermal Modeling and Performance Analysis of Interim Dry Storage and Geologic Disposal Facilities for Spent Nuclear Fuel
Si Y. Lee, Robert L. Sindelar, David C. Losey
Nuclear Technology | Volume 131 | Number 1 | July 2000 | Pages 124-151
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT00-A3108
The Impact of the Steam-Water Mixture Heterogeneity on the Results of Boiling Water Reactor Cell Calculations
Alexander O. Goltsev, Dmitry N. Martynov, Stanislav V. Marin, Andrei A. Lekomtsev
Nuclear Technology | Volume 131 | Number 2 | August 2000 | Pages 153-158
Technical Paper | Fission Reactors | doi.org/10.13182/NT00-A3109
Development of a Code with the Capability of Internal Assessment of Uncertainty
Francesco D'Auria, Walter Giannotti
Nuclear Technology | Volume 131 | Number 2 | August 2000 | Pages 159-196
Technical Paper | Reactor Safety | doi.org/10.13182/NT00-5
Parametric Studies on Plutonium Transmutation Using Uranium-Free Fuels in Light Water Reactors
Afroza Shelley, Hiroshi Akie, Hideki Takano, Hiroshi Sekimoto
Nuclear Technology | Volume 131 | Number 2 | August 2000 | Pages 197-209
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT00-A3111
Calculated Actinide and Fission Product Concentration Ratios for Gaseous Effluent Monitoring Using Monteburns 3.01
William S. Charlton, Robert T. Perry, Bryan L. Fearey, Theodore A. Parish
Nuclear Technology | Volume 131 | Number 2 | August 2000 | Pages 210-227
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT00-A3112
VVER1000/320 Operational Transient Simulation with the CATHARE Computer Program
Andrey A. Troshko, Yassin A. Hassan
Nuclear Technology | Volume 131 | Number 2 | August 2000 | Pages 228-238
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT00-A3113
Localization of a Vibrating Control Rod Pin in Pressurized Water Reactors Using the Neutron Flux and Current Noise
Vasiliy Arzhanov, Imre Pázsit, Ninos S. Garis
Nuclear Technology | Volume 131 | Number 2 | August 2000 | Pages 239-251
Technical Paper | Nuclear Plant Operations and Control | doi.org/10.13182/NT00-A3114
Rethinking High-Level Waste Disposal: Separate Disposal of High-Heat Radionuclides (90Sr and 137Cs)
Charles W. Forsberg
Nuclear Technology | Volume 131 | Number 2 | August 2000 | Pages 252-268
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT00-A3115
Prediction of In-Phantom Dose Distribution Using In-Air Neutron Beam Characteristics for Boron Neutron Capture Synovectomy
Jérôme M. Verbeke, Allen S. Chen, Jasmina L. Vujic, Ka-Ngo Leung
Nuclear Technology | Volume 131 | Number 2 | August 2000 | Pages 269-276
Technical Paper | Radiation Biology and Medicine | doi.org/10.13182/NT00-A3116
Temperature Reactivity Effects in Pebbles of a High-Temperature Reactor Fueled with Reactor-Grade Plutonium
E. E. Bende
Nuclear Technology | Volume 131 | Number 3 | September 2000 | Pages 279-296
Technical Paper | Fission Reactors | doi.org/10.13182/NT00-A3117
LOCA with Consequential or Delayed LOOP: Modeling of Accident Sequences and Associated Core Damage Frequency
Gerardo Martinez-Guridi, Pranab Samanta, Tsong-Lun Chu, Ji-Wu Yang
Nuclear Technology | Volume 131 | Number 3 | September 2000 | Pages 297-318
Technical Paper | Reactor Safety | doi.org/10.13182/NT00-A3118
Analysis of Kuosheng Large-Break Loss-of-Coolant Accident with MELCOR 1.8.4
Te-Chuan Wang, Shih-Jen Wang, Chun-Sheng Chien
Nuclear Technology | Volume 131 | Number 3 | September 2000 | Pages 319-331
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT00-A3119
Formulas Giving Buildup Factor for Double-Layered Shields
Mevlut Guvendik, Nicholas Tsoulfanidis
Nuclear Technology | Volume 131 | Number 3 | September 2000 | Pages 332-336
Technical Paper | Radiation Protection | doi.org/10.13182/NT00-A3120
Effect of Depleted-Uranium Dioxide Particulate Fill on Spent-Nuclear-Fuel Waste Packages
Nuclear Technology | Volume 131 | Number 3 | September 2000 | Pages 337-353
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT00-A3121
The Remodeling and Basic Characteristics of the Heavy Water Neutron Irradiation Facility of the Kyoto Univesity Research Reactor, Mainly for Neutron Capture Therapy
Tooru Kobayashi, Yoshinori Sakurai, Keiji Kanda, Yoshiaki Fujita, Koji Ono
Nuclear Technology | Volume 131 | Number 3 | September 2000 | Pages 354-378
Technical Paper | Radiation Biology and Medicine | doi.org/10.13182/NT00-A3122
University Research Reactors: Issues and Challenges
John A. Bernard, Lin-Wen Hu
Nuclear Technology | Volume 131 | Number 3 | September 2000 | Pages 379-384
Technical Note | Fission Reactors | doi.org/10.13182/NT00-A3123
The Physics of Plutonium Fuels - A Review of Organization for Economic Cooperation and Development/Nuclear Energy Agency Activities
Kevin Hesketh, Marc Delpech, Enrico Sartori
Nuclear Technology | Volume 131 | Number 3 | September 2000 | Pages 385-394
Technical Note | Fuel Cycle and Management | doi.org/10.13182/NT00-A3124