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Conference Spotlight
2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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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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Latest News
IAEA again raises global nuclear power projections
Noting recent momentum behind nuclear power, the International Atomic Energy Agency has revised up its projections for the expansion of nuclear power, estimating that global nuclear operational capacity will more than double by 2050—reaching 2.6 times the 2024 level—with small modular reactors expected to play a pivotal role in this high-case scenario.
IAEA director general Rafael Mariano Grossi announced the new projections, contained in the annual report Energy, Electricity, and Nuclear Power Estimates for the Period up to 2050 at the 69th IAEA General Conference in Vienna.
In the report’s high-case scenario, nuclear electrical generating capacity is projected to increase to from 377 GW at the end of 2024 to 992 GW by 2050. In a low-case scenario, capacity rises 50 percent, compared with 2024, to 561 GW. SMRs are projected to account for 24 percent of the new capacity added in the high case and for 5 percent in the low case.
J. E. Selle, P. Angelini, R. H. Rainey, J. I. Federer, A. R. Olsen
Nuclear Technology | Volume 45 | Number 3 | October 1979 | Pages 269-286
Technical Paper | Fuel Cycle | doi.org/10.13182/NT79-A32296
Articles are hosted by Taylor and Francis Online.
The use of a gamma active radionuclide with nuclear fuel has been proposed as a way to inhibit unauthorized diversion of the fuel and thus provide proliferation deterrence. Proposed dose rate ranges have varied from small additions to increase detectability of diverted material up to large additions to provide lethal doses in a relatively short exposure time. Some of the practical aspects of incorporating spikants into nuclear fuel are examined in an attempt to identify any technically adverse consequences of their use. Selection of potential spikants was made by the application of some somewhat arbitrary radiation criteria to 64 candidate spikants followed by an analysis of the chemical and physical state of each potential spikant. As a result of this analysis, the list of candidates was narrowed to 60Co, 106Ru, and 144Ce. Following this, we investigated the practical aspects of the use of these three spikants in nuclear fuel. Among the subjects considered are dose rates available from fuel elements, fission product buildup, chemical behavior of spikants during reprocessing, and possible effects of spikants on refabrication and on the fuel properties. Neither 106Ru nor 144Ce is present in sufficient quantity to produce the maximum radiation dose rate level considered. Nonradioactive nuclides of ruthenium and cerium dilute the radioactive nuclides to 2 to 4% of the total element in the fission products 2 yr after removal from the reactor. Recycling ruthenium and cerium will result in dilution of the radionuclides even further by a buildup of stable isotopes of each of these elements. Approximately 50% of the fission product ruthenium and 3 to 5% of the cerium can be coprocessed with the fuel, while cobalt cannot be coprocessed at all. No single radionuclide was found to be preferred in all stages of reprocessing and refabrication. To provide deterrence in all stages of reprocessing and refabrication, a duplex spiking process appears necessary, in which two different spikants, 106Ru and 60Co, are used in different portions of reprocessing. The use of nominal amounts of ruthenium or cobalt as spikants is not expected to adversely affect fuel performance.
