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Meeting Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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
The U.S. Million Person Study of Low-Dose-Rate Health Effects
There is a critical knowledge gap regarding the health consequences of exposure to radiation received gradually over time. While there is a plethora of studies on the risks of adverse outcomes from both acute and high-dose exposures, including the landmark study of atomic bomb survivors, these are not characteristic of the chronic exposure to low-dose radiation encountered in occupational and public settings. In addition, smaller cohorts have limited numbers leading to reduced statistical power.
Nicholas Chornoboy, Alexandra Levinsky, Charles Kitson, Blair P. Bromley
Nuclear Technology | Volume 204 | Number 1 | October 2018 | Pages 110-118
Technical Note | doi.org/10.1080/00295450.2018.1454229
Articles are hosted by Taylor and Francis Online.
Lattice physics depletion calculations were performed to obtain postburnup fuel compositions for several candidate advanced heavy water reactor fuels. These fuel compositions were used as input for a deep geological repository (DGR) modeling tool for hydrogeology simulations to simulate the transport of radionuclides to the surface, to find the radionuclides that reach the surface path through the biosphere, and to estimate the hypothetical dose rate to humans located above the DGR.
Three primary factors were found to contribute to surface dose rate: burnup, composition of the primary waste matrix, and percentage of thorium in the fuel. Higher burnup and thorium percentage contribute to increased surface dose rates through increased 129I production, while a primarily uranium waste matrix increases surface dose rate through faster dissolution leading to increased radionuclide release rate from the fuel. For all the hypothetical fuels investigated, the estimated dose rates are well within the Nuclear Waste Management Organization’s hypothetical DGR’s acceptance criterion of 0.3 mSv/year.