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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
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver 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!
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Latest News
TerraPower begins U.K. regulatory approval process
Seattle-based TerraPower signaled its interest this week in building its Natrium small modular reactor in the United Kingdom, the company announced.
TerraPower sent a letter to the U.K.’s Department for Energy Security and Net Zero, formally establishing its intention to enter the U.K. generic design assessment (GDA) process. This is TerraPower’s first step in deployment of its Natrium technology—a 345-MW sodium fast reactor coupled with a molten salt energy storage unit—on the international stage.
Richard Simms, Stephen M. Gehl, Robert K. Lo, Alan B. Rothman
Nuclear Technology | Volume 52 | Number 2 | February 1981 | Pages 228-245
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT81-A32667
Articles are hosted by Taylor and Francis Online.
Test L5 simulated a hypothetical fast test reactor (FTR) loss-of-flow (LOF) accident using three (Pu,U)O2 fuel elements. The test elements were irradiated at 40 kW/m before Transient Reactor Test Facility Test L5 in the General Electric Test Reactor to 8 at.% burnup. The active fuel column length of the test elements was ∼50 mm shorter than the active length for the FTR. The test elements had a fuel microstructure approximating moderate-power-structure FTR fuel In the LOF accident sequence for the FTR, fuel slumping in the high-power subassemblies causes a power excursion. Test L5 examined the fuel motion for conditions associated with the moderate-power FTR subassemblies in the accident. Dispersals of moderate-power fuel can reduce the accident severity. Data from test vehicle sensors, fuel motion detectors, and a post-test examination were used to reconstruct the sequence of events within the test zone. The test data indicated that a fuel dispersal occurred after reaching a peak power of six-times nominal The fuel motion was apparently driven by the release of fission-product gases entrained in the fuel matrix, since a fuel-vapor-pressure driving force was not significant in this test. The fuel remains showed a range of microstructural changes which were especially useful in inferring the sequence of post-failure events.