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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.
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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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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IAEA: Gunfire, drone attack at Ukraine’s Zaporizhzhia nuclear plant
The International Atomic Energy Agency team at Ukraine’s Zaporizhzhia nuclear power plant (ZNPP) reported hearing gunfire near the site this morning while a drone hit the plant’s training center.
In a news release today, IAEA director general Rafael Mariano Grossi said this is the third drone to target the training center, located just outside the site perimeter, so far this year. He called for an immediate end to drones being flown over or near nuclear facilities.
K. Linga Murty
Nuclear Technology | Volume 67 | Number 1 | October 1984 | Pages 124-131
Technical Paper | Material | doi.org/10.13182/NT84-A33535
Articles are hosted by Taylor and Francis Online.
Improvements in both the yield strength and ductility were noted in mild steel at elevated temperatures (≳315 K) following neutron irradiation to 2 × 1022 n/m2, in contrast to hitherto observed radiation hardening and embrittlement. This beneficial effect was shown to be due to the interaction of interstitial impurities with radiation-produced defects resulting in reduced concentration of interstitial carbon and nitrogen in solution, and thus blue brittleness is suppressed following radiation exposure. Consequently, the energy absorbed by the irradiated material (a measure of toughness) improved at these temperatures. In the temperature range examined, namely from 300 to 550 K, Lüders strain increased following neutron irradiation. While the Lüders strain of unirradiated material exhibited a peak at ∼460 K due to dynamic strain aging, it decreased continuously with test temperature following neutron irradiation. Radiation exposure resulted in decreased rates of work hardening at all of the test temperatures. Peaks in the temperature dependence of the work-hardening parameter are noted for the unirradiated material in the serrated flow regime. Thermal recovery of radiation damage resulted in increased rates of work hardening at elevated temperatures.