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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.
Meeting Spotlight
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?
K. L. Nash, S. Fried, A. M. Friedman, N. Susak, P. Rickert, J. C. Sullivan
Nuclear Technology | Volume 60 | Number 2 | February 1983 | Pages 257-266
Technical Paper | Radiation Effects and Their Relationship to Geological Repository / Radioactive Waste Management | doi.org/10.13182/NT83-A33081
Articles are hosted by Taylor and Francis Online.
The rates at which 241Am and 239Pu are leached by triply distilled water from a candidate borosilicate glass 76-101 can be adequately correlated by the exponential, An = An0l−kt, where An is the concentration of the actinide in molar mass per square centimetre. The values for the parameters An0 and k are 2.45 × 10−9 M/cm2 and 0.024 ± 0.001 h−1, respectively, over the period of 1 to 24 h. When the glass samples are irradiated with gamma rays from a 60Co source of 1 Mrad/h, values of the parameters (1-to 24-h irradiation time) are A0 = 5.6 × 10−9M/cm2, k = 0.103 ± 0.004 h−1 for 239Pu and A0 = 2.2 × 10−11 M/cm2, k = 0.104 ± 0.003 h−1 for 241 Am.