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
Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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
Apr 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
May 2025
Nuclear Technology
April 2025
Fusion Science and Technology
Latest News
First astatine-labeled compound shipped in the U.S.
The Department of Energy’s National Isotope Development Center (NIDC) on March 31 announced the successful long-distance shipment in the United States of a biologically active compound labeled with the medical radioisotope astatine-211 (At-211). Because previous shipments have included only the “bare” isotope, the NIDC has described the development as “unleashing medical innovation.”
Jump to:
Use of Thoria-Urania Fuels in PWRs: A General Review of a NERI Project to Assess Feasible Core Designs, Economics, Fabrication Methods, In-Pile Thermal/Mechanical Behavior, and Waste Form Characteristics
Philip E. MacDonald, Chan Bock Lee
Nuclear Technology | Volume 147 | Number 1 | July 2004 | Pages 1-7
Technical Paper | Thoria-Urania NERI | doi.org/10.13182/NT04-A3510
Core Designs and Economic Analyses of Homogeneous Thoria-Urania Fuel in Light Water Reactors
Mehmet Saglam, Joe J. Sapyta, Stewart W. Spetz, Lawrence A. Hassler
Nuclear Technology | Volume 147 | Number 1 | July 2004 | Pages 8-19
Technical Paper | Thoria-Urania NERI | doi.org/10.13182/NT03-29
Microheterogeneous Thoria-Urania Fuels for Pressurized Water Reactors
Eugene Shwageraus, Xianfeng Zhao, Michael J. Driscoll, Pavel Hejzlar, Mujid S. Kazimi, J. Stephen Herring
Nuclear Technology | Volume 147 | Number 1 | July 2004 | Pages 20-36
Technical Paper | Thoria-Urania NERI | doi.org/10.13182/NT04-A3512
Alternative Applications of Homogeneous Thoria-Urania Fuel in Light Water Reactors to Enhance the Economics of the Thorium Fuel Cycle
Hyung-Kook Joo, Jae-Man Noh, Jae-Woon Yoo, Jin-Young Cho, Sang-Yoon Park, Moon-Hee Chang
Nuclear Technology | Volume 147 | Number 1 | July 2004 | Pages 37-52
Technical Paper | Thoria-Urania NERI | doi.org/10.13182/NT03-30
Use of Thorium for Transmutation of Plutonium and Minor Actinides in PWRs
Eugene Shwageraus, Pavel Hejzlar, Mujid S. Kazimi
Nuclear Technology | Volume 147 | Number 1 | July 2004 | Pages 53-68
Technical Paper | Thoria-Urania NERI | doi.org/10.13182/NT04-A3514
Weapons-Grade Plutonium-Thorium PWR Assembly Design and Core Safety Analysis
David Dziadosz, Timothy N. Ake, Mehmet Saglam, Joe J. Sapyta
Nuclear Technology | Volume 147 | Number 1 | July 2004 | Pages 69-83
Technical Paper | Thoria-Urania NERI | doi.org/10.13182/NT147-69
Thorium-Based Transmuter Fuels for Light Water Reactors
J. Stephen Herring, Philip E. MacDonald, Kevan D. Weaver
Nuclear Technology | Volume 147 | Number 1 | July 2004 | Pages 84-101
Technical Paper | Thoria-Urania NERI | doi.org/10.13182/NT04-A3516
Costs for Manufacturing Thorium-Uranium Dioxide Fuels for Light Water Reactors
Edward J. Lahoda
Nuclear Technology | Volume 147 | Number 1 | July 2004 | Pages 102-112
Technical Paper | Thoria-Urania NERI | doi.org/10.13182/NT04-A3517
Fabrication and Thermal Conductivity of (Th,U)O2 Pellets
Jae Ho Yang, Ki Won Kang, Kun Woo Song, Chan Bock Lee, Youn Ho Jung
Nuclear Technology | Volume 147 | Number 1 | July 2004 | Pages 113-119
Technical Paper | Thoria-Urania NERI | doi.org/10.13182/NT04-A3518
The Behavior of ThO2-Based Fuel Rods During Normal Operation and Transient Events in LWRs
Yun Long, Larry J. Siefken, Pavel Hejzlar, Eric P. Loewen, Judith K. Hohorst, Philip E. MacDonald, Mujid S. Kazimi
Nuclear Technology | Volume 147 | Number 1 | July 2004 | Pages 120-139
Technical Paper | Thoria-Urania NERI | doi.org/10.13182/NT04-A3519
Irradiation Behavior of Thoria-Urania Fuel in a PWR
Chan Bock Lee, Yong Sik Yang, Young Min Kim, Dae Ho Kim, Youn Ho Jung
Nuclear Technology | Volume 147 | Number 1 | July 2004 | Pages 140-148
Technical Paper | Thoria-Urania NERI | doi.org/10.13182/NT04-A3520
Xenon Diffusivity in Thoria-Urania Fuel
Heemoon Kim, Kwangheon Park, Bong Goo Kim, Yong Sun Choo, Keon Sik Kim, Kun Woo Song, Kwon Pyo Hong, Young Hwan Kang, Kwangil Ho
Nuclear Technology | Volume 147 | Number 1 | July 2004 | Pages 149-156
Technical Paper | Thoria-Urania NERI | doi.org/10.13182/NT04-A3521
Aqueous Dissolution of Urania-Thoria Nuclear Fuel
Paul A. Demkowicz, James L. Jerden, Jr., James C. Cunnane, Noriko Shibuya, Ronald Baney, James Tulenko
Nuclear Technology | Volume 147 | Number 1 | July 2004 | Pages 157-170
Technical Paper | Thoria-Urania NERI | doi.org/10.13182/NT04-A3522
Neutronic and Logistic Proposal for Transmutation of Plutonium from Spent Nuclear Fuel as Mixed-Oxide Fuel in Existing Light Water Reactors
Holly R. Trellue
Nuclear Technology | Volume 147 | Number 2 | August 2004 | Pages 171-180
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT04-A3523
Computational Fluid Dynamics for the Analysis of Light Water Reactor Flows
Constantine P. Tzanos
Nuclear Technology | Volume 147 | Number 2 | August 2004 | Pages 181-190
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT04-A3524
Validation of Heat Transfer Models in Narrow Gap for RELAP/SCDAPSIM/MOD3.2
Tamio Kohriyama, Michio Murase, Takashi Nagae, Yukimitsu Okano, Alexandre Ezzidi
Nuclear Technology | Volume 147 | Number 2 | August 2004 | Pages 191-201
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT04-A3525
Hydrogen Generation in Reflooding Experiments with LWR-Type Rod Bundles (QUENCH Program)
Leo K. Sepold, Alexei Miassoedov, Gerhard Schanz, Ulrike Stegmaier, Martin Steinbrück, Juri Stuckert, Christoph Homann
Nuclear Technology | Volume 147 | Number 2 | August 2004 | Pages 202-215
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT04-A3526
Identification of Loss-of-Coolant Accidents in LWRs by Inverse Models
Wojciech Cholewa, Wiktor Frid, Marcin Bednarski
Nuclear Technology | Volume 147 | Number 2 | August 2004 | Pages 216-226
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT04-A3527
Software Safety Analysis of Digital Protection System Requirements Using a Qualitative Formal Method
Jang-Soo Lee, Kee-Choon Kwon, Sung-Deok Cha
Nuclear Technology | Volume 147 | Number 2 | August 2004 | Pages 227-239
Technical Paper | Nuclear Plant Operations and Control | doi.org/10.13182/NT04-A3528
Design and Validation of Optimized Feedforward with Robust Feedback Control of a Nuclear Reactor
Roman Shaffer, Weidong He, Robert M. Edwards
Nuclear Technology | Volume 147 | Number 2 | August 2004 | Pages 240-257
Technical Paper | Nuclear Plant Operations and Control | doi.org/10.13182/NT04-A3529
Water Sorption and Gamma Radiolysis Studies for Uranium Oxides
Alan S. Icenhour, L. M. Toth, Huimin Luo
Nuclear Technology | Volume 147 | Number 2 | August 2004 | Pages 258-268
Technical Paper | Nuclear Plant Operations and Control | doi.org/10.13182/NT04-A3530
Nitrogen-16 Generation and Transport and Associated Shielding Requirements in a Supercritical-Water-Cooled Reactor
Benjamin Fischer, Marci Smolinski, Jacopo Buongiorno
Nuclear Technology | Volume 147 | Number 2 | August 2004 | Pages 269-283
Technical Paper | Nuclear Plant Operations and Control | doi.org/10.13182/NT04-A3531
Development of a Cobalt Dicarbollide/Polyethylene Glycol Solvent Extraction Process for Separation of Cesium and Strontium to Support Advanced Aqueous Reprocessing
Jack D. Law, R. Scott Herbst, Dean R. Peterman, Rich D. Tillotson, Terry A. Todd
Nuclear Technology | Volume 147 | Number 2 | August 2004 | Pages 284-290
Technical Paper | Reprocessing | doi.org/10.13182/NT04-A3532
Eddy Current Measurements of Corrosion and Metal Loss in Zircaloy Cladding with Ferromagnetic Crud
Suresh K. Yagnik, Duane P. Johnson, John A. Kervinen
Nuclear Technology | Volume 147 | Number 2 | August 2004 | Pages 291-300
Technical Paper | Materials for Nuclear Systems | doi.org/10.13182/NT04-A3533
Medium-Power Lead-Alloy Reactors: Missions for This Reactor Technology
Neil E. Todreas, Philip E. MacDonald, Pavel Hejzlar, Jacopo Buongiorno, Eric P. Loewen
Nuclear Technology | Volume 147 | Number 3 | September 2004 | Pages 305-320
Technical Paper | Medium-Power Lead-Alloy Reactors | doi.org/10.13182/NT04-A3534
Design Strategy and Constraints for Medium-Power Lead-Alloy–Cooled Actinide Burners
Pavel Hejzlar, Jacopo Buongiorno, Philip E. MacDonald, Neil E. Todreas
Nuclear Technology | Volume 147 | Number 3 | September 2004 | Pages 321-343
Technical Paper | Medium-Power Lead-Alloy Reactors | doi.org/10.13182/NT147-321
Performance of the Lead-Alloy-Cooled Reactor Concept Balanced for Actinide Burning and Electricity Production
Pavel Hejzlar, Cliff B. Davis
Nuclear Technology | Volume 147 | Number 3 | September 2004 | Pages 344-367
Technical Paper | Medium-Power Lead-Alloy Reactors | doi.org/10.13182/NT04-A3536
Fertile-Free Fast Lead-Cooled Incinerators for Efficient Actinide Burning
Antonino Romano, Pavel Hejzlar, Neil E. Todreas
Nuclear Technology | Volume 147 | Number 3 | September 2004 | Pages 368-387
Technical Paper | Medium-Power Lead-Alloy Reactors | doi.org/10.13182/NT04-1
Medium-Power Lead-Alloy Fast Reactor Balance-of-Plant Options
Vaclav Dostal, Pavel Hejzlar, Neil E. Todreas, Jacopo Buongiorno
Nuclear Technology | Volume 147 | Number 3 | September 2004 | Pages 388-405
Technical Paper | Medium-Power Lead-Alloy Reactors | doi.org/10.13182/NT147-388
Studies of Polonium Removal from Molten Lead-Bismuth for Lead-Alloy-Cooled Reactor Applications
Jacopo Buongiorno, Eric P. Loewen, Kenneth Czerwinski, Christopher Larson
Nuclear Technology | Volume 147 | Number 3 | September 2004 | Pages 406-417
Technical Paper | Medium-Power Lead-Alloy Reactors | doi.org/10.13182/NT04-A3539
An Overview of Corrosion Issues for the Design and Operation of High-Temperature Lead- and Lead-Bismuth-Cooled Reactor Systems
Ronald G. Ballinger, Jeongyoun Lim
Nuclear Technology | Volume 147 | Number 3 | September 2004 | Pages 418-435
Technical Paper | Medium-Power Lead-Alloy Reactors | doi.org/10.13182/NT04-A3540
Corrosion Studies in Support of Medium-Power Lead-Alloy-Cooled Reactor
Eric P. Loewen, Ronald G. Ballinger, Jeongyoun Lim
Nuclear Technology | Volume 147 | Number 3 | September 2004 | Pages 436-456
Technical Paper | Medium-Power Lead-Alloy Reactors | doi.org/10.13182/NT04-A3541
A Qualitative Reactivity and Isotopic Assessment of Fuels for Lead-Alloy-Cooled Fast Reactors
Kevan D. Weaver, Philip E. MacDonald
Nuclear Technology | Volume 147 | Number 3 | September 2004 | Pages 457-469
Technical Paper | Medium-Power Lead-Alloy Reactors | doi.org/10.13182/NT04-A3542