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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
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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
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?
Ivars Neretnieks
Nuclear Technology | Volume 62 | Number 1 | July 1983 | Pages 110-115
]Technical Note | Radioactive Waste Management | doi.org/10.13182/NT83-A33238
Articles are hosted by Taylor and Francis Online.
In a repository for high-level nuclear waste in bedrock that may carry water, the waste will eventually come in contact with water. Radionuclides will dissolve in the water and migrate away from the repository. In crystalline rock in Sweden, the waters at repository depths are reducing. Many of the important radionuclides, e.g., neptunium, uranium, and technetium, have very low solubilities under these conditions (parts per billion levels). The solubility will considerably limit the transport of these species. If by some means the conditions were to change from reducing to oxidizing, the solubility of these species would increase very much, in some cases by 4 to 6 orders of magnitude. Under such circumstances, these nuclides would escape much faster. We have investigated one possible way in which the redox conditions might change, i.e., spent fuel has a considerable alpha activity, which may radiolyze water and produce oxidizing agents such as hydrogen peroxide. The hydrogen peroxide will make the water oxidizing. The compensating factor is ferrous iron in the bedrock. In the investigation of the interaction of these two species, a con-ceptional and a mathematical model is developed describing the movement of the redox front downstream of a repository. A sample calculation based on minimum measured ferrous iron contents in the bedrock and computed (conservatively on the high side) hydrogen peroxide production shows that the redox front could move several tens of metres downstream in the million-year perspective. The rate of radiolysis would decrease considerably if the spent fuel is not wetted to the high degree assumed in the calculations. The results in the sample calculation should be seen as maximum values for the type of repository considered