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Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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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Reboot: Nuclear needs a success . . . anywhere
The media have gleefully resurrected the language of a past nuclear renaissance. Beyond the hype and PR, many people in the nuclear community are taking a more measured view of conditions that could lead to new construction: data center demand, the proliferation of new reactor designs and start-ups, and the sudden ascendance of nuclear energy as the power source everyone wants—or wants to talk about.
Once built, large nuclear reactors can provide clean power for at least 80 years—outlasting 10 to 20 presidential administrations. Smaller reactors can provide heat and power outputs tailored to an end user’s needs. With all the new attention, are we any closer to getting past persistent supply chain and workforce issues and building these new plants? And what will the election of Donald Trump to a second term as president mean for nuclear?
As usual, there are more questions than answers, and most come down to money. Several developers are engaging with the Nuclear Regulatory Commission or have already applied for a license, certification, or permit. But designs without paying customers won’t get built. So where are the customers, and what will it take for them to commit?
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.
