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 Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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
Jan 2025
Jul 2024
Latest Journal Issues
Nuclear Science and Engineering
February 2025
Nuclear Technology
January 2025
Fusion Science and Technology
Latest News
NRC issues subsequent license renewal to Monticello plant
The Nuclear Regulatory Commission has renewed for a second time the operating license for Unit 1 of Minnesota’s Monticello nuclear power plant.
Jump to:
Annular Fast Reactor Cores with Low Sodium Void Worth for TRU Burning
Ser Gi Hong, Sang Ji Kim, Yeong Il Kim
Nuclear Technology | Volume 162 | Number 1 | April 2008 | Pages 1-25
Technical Paper | Reactor Safety | doi.org/10.13182/NT162-1-25
A Markov Model Approach to Proliferation-Resistance Assessment of Nuclear Energy Systems
Meng Yue, Lap-Yan Cheng, Robert A. Bari
Nuclear Technology | Volume 162 | Number 1 | April 2008 | Pages 26-44
Technical Paper | Reactor Safety | doi.org/10.13182/NT08-A3931
Multiobjective Optimization of a Wire-Wrapped LMR Fuel Assembly
Wasim Raza, Kwang-Yong Kim
Nuclear Technology | Volume 162 | Number 1 | April 2008 | Pages 45-52
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT08-A3932
A TRU-Zr Metal-Fuel Sodium-Cooled Fast Subcritical Advanced Burner Reactor
W. M. Stacey, W. Van Rooijen, T. Bates, E. Colvin, J. Dion, J. Feener, E. Gayton, D. Gibbs, C. Grennor, J. Head, F. Hope, J. Ireland, A. Johnson, B. Jones, N. Mejias, C. Myers, A. Schmitz, C. Sommer, T. Sumner, L. Tschaepe
Nuclear Technology | Volume 162 | Number 1 | April 2008 | Pages 53-79
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT08-A3933
Nanofluids for Enhanced Economics and Safety of Nuclear Reactors: An Evaluation of the Potential Features, Issues, and Research Gaps
Jacopo Buongiorno, Lin-Wen Hu, Sung Joong Kim, Ryan Hannink, Bao Truong, Eric Forrest
Nuclear Technology | Volume 162 | Number 1 | April 2008 | Pages 80-91
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT08-A3934
Assessment of MARS-GCR Code for a New Reactor Cavity Cooling System Design
Yun-Je Cho, Hyoung-Kyu Cho, Goon-Cherl Park
Nuclear Technology | Volume 162 | Number 1 | April 2008 | Pages 92-106
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT08-A3935
Assessment of a High-Throughput Electrorefining Concept for a Spent Metallic Nuclear Fuel - I: Computational Fluid Dynamics Analysis
J. H. Lee, Y. H. Kang, S. C. Hwang, H. S. Lee, E. H. Kim, S. W. Park
Nuclear Technology | Volume 162 | Number 1 | April 2008 | Pages 107-116
Technical Paper | Reprocessing | doi.org/10.13182/NT08-A3936
Recovery of U-Pu Alloy from MOX Using a Pyroprocess Series
Shinichi Kitawaki, Tadahiro Shinozaki, Mineo Fukushima, Tsuyoshi Usami, Noboru Yahagi, Masaki Kurata
Nuclear Technology | Volume 162 | Number 2 | May 2008 | Pages 118-123
Technical Paper | First International Pyroprocessing Research Conference | doi.org/10.13182/NT08-A3937
Engineering-Scale Liquid Cadmium Cathode Experiments
D. Vaden, S. X. Li, B. R. Westphal, K. B. Davies, T. A. Johnson, D. M. Pace
Nuclear Technology | Volume 162 | Number 2 | May 2008 | Pages 124-128
Technical Paper | First International Pyroprocessing Research Conference | doi.org/10.13182/NT08-A3938
Cyclic Voltammetry Behavior of Americium at a Liquid Cadmium Electrode in LiCl-KCl Eutectic Melts
Hirokazu Hayashi, Mitsuo Akabori, Kazuo Minato
Nuclear Technology | Volume 162 | Number 2 | May 2008 | Pages 129-134
Technical Paper | First International Pyroprocessing Research Conference | doi.org/10.13182/NT08-A3939
Application of Graphite as a Cathode Material for Electrorefining of Uranium
J. H. Lee, Y. H. Kang, S. C. Hwang, J. B. Shim, E. H. Kim, S. W. Park
Nuclear Technology | Volume 162 | Number 2 | May 2008 | Pages 135-143
Technical Paper | First International Pyroprocessing Research Conference | doi.org/10.13182/NT08-A3940
Experimental Observations on the Roles of the Cadmium Pool in the Mark-IV Electrorefiner
Shelly X. Li
Nuclear Technology | Volume 162 | Number 2 | May 2008 | Pages 144-152
Technical Paper | First International Pyroprocessing Research Conference | doi.org/10.13182/NT08-A3941
Effect of Process Variables During the Head-End Treatment of Spent Oxide Fuel
B. R. Westphal, K. J. Bateman, C. D. Morgan, J. F. Berg, P. J. Crane, D. G. Cummings, J. J. Giglio, M. W. Huntley, R. P. Lind, D. A. Sell
Nuclear Technology | Volume 162 | Number 2 | May 2008 | Pages 153-157
Technical Paper | First International Pyroprocessing Research Conference | doi.org/10.13182/NT08-A3942
Fractional Release Behavior of Volatile and Semivolatile Fission Products During a Voloxidation and OREOX Treatment of Spent PWR Fuel
Kee Chan Song, Geun Il Park, Jung Won Lee, Jang Jin Park, Myung Seung Yang
Nuclear Technology | Volume 162 | Number 2 | May 2008 | Pages 158-168
Technical Paper | First International Pyroprocessing Research Conference | doi.org/10.13182/NT08-A3943
Application of Electrochemical Reduction to Produce Metal Fuel Material from Actinide Oxides
Yoshiharu Sakamura, Takashi Omori, Tadashi Inoue
Nuclear Technology | Volume 162 | Number 2 | May 2008 | Pages 169-178
Technical Paper | First International Pyroprocessing Research Conference | doi.org/10.13182/NT162-169
Modeling the Pyrochemical Reduction of Spent UO2 Fuel in a Pilot-Scale Reactor
Michael F. Simpson, Steven D. Herrmann
Nuclear Technology | Volume 162 | Number 2 | May 2008 | Pages 179-183
Technical Paper | First International Pyroprocessing Research Conference | doi.org/10.13182/NT162-179
An Electrochemical Reduction of Uranium Oxide in the Advanced Spent-Fuel Conditioning Process
Sang Mun Jeong, Jin-Mok Hur, Sun Seok Hong, Dae Seung Kang, Myoung Soo Choung, Chung-Seok Seo, Ji-Sup Yoon, Seong-Won Park
Nuclear Technology | Volume 162 | Number 2 | May 2008 | Pages 184-191
Technical Paper | First International Pyroprocessing Research Conference | doi.org/10.13182/NT162-184
Chemical Behavior of Fission Products in the Pyrochemical Process
Jin-Mok Hur, Tack-Jin Kim, In-Kyu Choi, Jae Bum Do, Sun-Seok Hong, Chung-Seok Seo
Nuclear Technology | Volume 162 | Number 2 | May 2008 | Pages 192-198
Technical Paper | First International Pyroprocessing Research Conference | doi.org/10.13182/NT08-A3947
The Ceramic Waste Form Process at Idaho National Laboratory
Stephen Priebe, Ken Bateman
Nuclear Technology | Volume 162 | Number 2 | May 2008 | Pages 199-207
Technical Paper | First International Pyroprocessing Research Conference | doi.org/10.13182/NT08-A3948
A New Approach to Minimize Pyroprocessing Waste Salts Through a Series of Fission Product Removal Process
Eung-Ho Kim, Geun-Il Park, Yung-Zun Cho, Hee-Chul Yang
Nuclear Technology | Volume 162 | Number 2 | May 2008 | Pages 208-218
Technical Paper | First International Pyroprocessing Research Conference | doi.org/10.13182/NT08-A3949
Alternative Technology for the Treatment of Waste LiCl Salt by Using Gelation with a Si-P-Al Material System and a Subsequent Thermal Conditioning Method
In-Tae Kim, Hwan-Seo Park, Seong-Won Park, Eung-Ho Kim
Nuclear Technology | Volume 162 | Number 2 | May 2008 | Pages 219-228
Technical Paper | First International Pyroprocessing Research Conference | doi.org/10.13182/NT08-A3950
Absorption Characteristics of Fission Product Elements on Zeolite
Takeshi Tsukada, Keiju Takahashi
Nuclear Technology | Volume 162 | Number 2 | May 2008 | Pages 229-243
Technical Paper | First International Pyroprocessing Research Conference | doi.org/10.13182/NT08-A3951
Synthesis of Actinide Nitrides in Molten Cadmium
Yasuo Arai, Takashi Iwai, Mitsuo Akabori, Kazuo Minato
Nuclear Technology | Volume 162 | Number 2 | May 2008 | Pages 244-249
Technical Paper | First International Pyroprocessing Research Conference | doi.org/10.13182/NT08-A3952
A Feasibility Study for the Development of Alternative Methods to Treat a Spent TRISO Fuel
Jong-Hyeon Lee, Joon-Bo Shim, Eung-Ho Kim, Jae-Hyung Yoo, Seong-Won Park, Christine T. Snyder
Nuclear Technology | Volume 162 | Number 2 | May 2008 | Pages 250-258
Technical Paper | First International Pyroprocessing Research Conference | doi.org/10.13182/NT08-A3953
Current Status of Pyrochemical Reprocessing Research in India
K. Nagarajan, T. Subramanian, B. Prabhakara Reddy, P. R. Vasudeva Rao, Baldev Raj
Nuclear Technology | Volume 162 | Number 2 | May 2008 | Pages 259-263
Technical Note | First International Pyroprocessing Research Conference | doi.org/10.13182/NT08-A3954
Characteristics and Sinterability of MOX Powder Prepared by the Microwave Heating Denitration Method
Koichi Asakura, Yoshiyuki Kato, Hirotaka Furuya
Nuclear Technology | Volume 162 | Number 3 | June 2008 | Pages 265-275
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT08-A3955
Stress Analysis of Coated Particle Fuel in Graphite of High-Temperature Reactors
B. Boer, A. M. Ougouag, J. L. Kloosterman, G. K. Miller
Nuclear Technology | Volume 162 | Number 3 | June 2008 | Pages 276-292
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT08-A3956
Assessing the Proliferation Resistance of Nuclear Fuel Cycle Systems Using a Fuzzy Logic-Based Barrier Method
Jun Li, Man-Sung Yim, David McNelis
Nuclear Technology | Volume 162 | Number 3 | June 2008 | Pages 293-307
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT08-A3957
An Analysis of Possible Impacts of Power Uprate on the Distributions of Erosion-Corrosion Wear Sites for a BWR Through CFD Simulation
Yuh Ming Ferng, Yung Shin Tseng, Bau Shei Pei, S. Long Wang, Chunkuan Shih, Tsun Fu Hung
Nuclear Technology | Volume 162 | Number 3 | June 2008 | Pages 308-322
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT08-A3958
Using Genetic Algorithms to Optimize the Helium Loop of a Very High Temperature Reactor
Christine Mansilla
Nuclear Technology | Volume 162 | Number 3 | June 2008 | Pages 323-332
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT08-A3959
A Cleanup Machine Using Reverse Osmosis Method to Remove Silica from Boric Acid Tank at Maanshan Nuclear Power Station
Chung-Hsien Liang, Kuo-Hwa Su
Nuclear Technology | Volume 162 | Number 3 | June 2008 | Pages 333-341
Technical Paper | Nuclear Plant Operations and Control | doi.org/10.13182/NT08-A3960
Materials Challenges for Generation IV Nuclear Energy Systems
T. R. Allen, K. Sridharan, L. Tan, W. E. Windes, J. I. Cole, D. C. Crawford, Gary S. Was
Nuclear Technology | Volume 162 | Number 3 | June 2008 | Pages 342-357
Technical Paper | Materials for Nuclear Systems | doi.org/10.13182/NT08-A3961
Results of a Full-Scale Liquid-Metal Leak Test in a Neutron Spallation Source Containment
K. Samec
Nuclear Technology | Volume 162 | Number 3 | June 2008 | Pages 358-378
Technical Paper | Accelerators | doi.org/10.13182/NT08-A3962
Long-Term Uranium Supply Estimates
Erich A. Schneider, William C. Sailor
Nuclear Technology | Volume 162 | Number 3 | June 2008 | Pages 379-387
Technical Paper | Miscellaneous | doi.org/10.13182/NT08-A3963
