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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
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!
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Latest News
Discovering, Making, and Testing New Materials: SRNL’s Center For Hierarchical Waste Form Materials
Savannah River National Laboratory researchers are building on the laboratory’s legacy of using cutting-edge science to effectively immobilize nuclear waste in innovative ways. As part of the Center for Hierarchical Waste Form Materials, SRNL is leveraging its depth of experience in radiological waste management to explore new frontiers in the industry.
Jun Wang (Univ of Wisconsin, Madison), Anil Gurgen (MIT), Michael L. Corradini (Univ of Wisconsin, Madison), Koroush Shirvan (MIT)
Proceedings | 2018 International Congress on Advances in Nuclear Power Plants (ICAPP 2018) | Charlotte, NC, April 8-11, 2018 | Pages 755-762
In order to compare the thermal hydraulics system response to Accident Tolerant Fuel (ATF) materials, a benchmark was performed for early accident progression behavior given a Station Blackout scenario. Thermal hydraulic parameters such as the pressurizer pressure, reactor pressure vessel (RPV) water level, peak cladding temperature, and hydrogen mass generated were quantified by the TRACE code by a team at MIT and compared to MELCOR by a team at UW Madison. This benchmark comparison with TRACE and MELCOR used the same initial conditions for a simplified generic PWR plant model. This PWR model was based on a 2200MWth conventional light water reactor plant. The benchmark work included the input model development and the simulation comparisons for the thermal hydraulic response, pressurizer relief valve operation, and the clad oxidation. The Zircaloy cladding case and FeCrAl cladding case were compared in the current simulation. The result showed good agreement between TRACE and MELCOR for overall event timing and key parameters. The exothermic energy release from Zircaloy and FeCrAl clad oxidation were calculated and compared. The difference in oxidation energy between the clad materials was quite small when compared to decay heat values.