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
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
Meeting Spotlight
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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
Jun 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
July 2025
Nuclear Technology
June 2025
Fusion Science and Technology
Latest News
ANS announces 2025 Presidential Citations
One of the privileges of being president of the American Nuclear Society is awarding Presidential Citations to individuals who have demonstrated outstanding effort in some manner for the benefit of ANS or the nuclear community at large. Citations are conferred twice each year, at the Annual and Winter Meetings.
ANS President Lisa Marshall has named this season’s recipients, who will receive recognition at the upcoming Annual Conference in Chicago during the Special Session on Tuesday, June 17.
Alexander J. Mieloszyk, Mujid S. Kazimi
Nuclear Technology | Volume 191 | Number 3 | September 2015 | Pages 268-281
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT14-104
Articles are hosted by Taylor and Francis Online.
To provide steady-state fuel performance evaluations for the (ThU)O2-fueled Reduced moderation Boiling Water Reactor (RBWR-Th), modifications have been made to the FRAPCON-MIT code. In addition to the use of existing (ThU)O2 capabilities in FRAPCON-MIT, a radial power profile specific to the RBWR-Th was implemented. To more accurately model the corrosion acceleration due to high fast neutron fluence, the oxidation model was modified, and a new hydrogen uptake model was introduced. A preliminary assessment of an average RBWR-Th fuel rod shows the fuel temperature to remain below 1450 K and the fission gas release (FGR) to remain below 7%. However, because of the low free gas volume of the RBWR-Th rods, the plenum pressure is very sensitive to FGR and is shown to be capable of exceeding the coolant pressure. Of more concern is the high cladding hydrogen content that results from the acceleration of hydrogen pickup at relatively low burnups, which is caused by the high fast neutron fluence on the cladding in the RBWR-Th. This high hydrogen content leads to significant restrictions and, ultimately, elimination of the margin to acceptable accident limits, presenting a distinct challenge to the RBWR-Th design. A new cladding material, GNF-Ziron, from Global Nuclear Fuels (GNF) offers a potential solution to this challenge by delaying the acceleration of the hydrogen pickup. The potential benefits of using GNF-Ziron cladding are explored in a sensitivity study. This study illustrates that the selection of an appropriate cladding material for the RBWR-Th is crucial for its success.