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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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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.
John Brian Ainscough*, David Norman Coucill, David Anthony Howl, Arne Jensen, Ib Misfeldt
Nuclear Technology | Volume 61 | Number 3 | June 1983 | Pages 521-532
Technical Paper | New Directions in Nuclear Energy with Emphasis on Fuel Cycles / Economic | doi.org/10.13182/NT83-A33177
Articles are hosted by Taylor and Francis Online.
Duplex UO2 pellets, which consist of an outer enriched annulus and a depleted or natural core, can provide a solution to the problem of stress corrosion cracking failures, which have led to constraints being placed on ramp rates in power reactors. An analysis of the reactor physics and the performance of duplex pellets is presented in the context of a 17 × 17 pressurized water reactor fuel rod design. The study has been based on the particular type of duplex pellet in which the core and the annulus are physically separate; this is called “LOWI” after the Danish design. At low bumup, this fuel shows a significant improvement in power ramp performance compared with standard fuel. At higher bumup, the benefits are less certain but as the severity of the ramp will usually be less in high bumup fuel simply because of the reduced rating, the reduction in benefit may not be significant. If the gap between the core and annulus persists to high bumup, there will be no loss of benefit. Economic calculations and a cost-benefit analysis are presented to show the number of extra full-power hours of reactor operation that must be obtained in order to outweigh the additional fabrication costs associated with this fuel.