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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.
Manuel G. Vigil, Amado A. Trujillo, H. Richard Yoshimura
Nuclear Technology | Volume 61 | Number 3 | June 1983 | Pages 514-520
Technical Paper | New Directions in Nuclear Energy with Emphasis on Fuel Cycles / Radioactive Waste Management | doi.org/10.13182/NT83-A33176
Articles are hosted by Taylor and Francis Online.
Full-scale experimental measurements on the thermal effects of torch fires on a large spent nuclear fuel shipping cask have been obtained. The measured temperature data in the various materials of the multilayered cask are unique, since no torch tests have been previously performed on a cask. These data were obtained during a series of four torch tests that simulate a situation in which the relief valve of a liquefied gas tank railcar has been opened and the contents are vented and ignited so that the resultant torch impinges on the cask. An existing spent fuel cask was modified, and temperature data were obtained in the various materials of the multilayered cask using stainless-steel sheathed thermocouples. Results of these tests indicated that the surface temperatures for the cask with a voided neutron shield were about twice as high as those for a cask having a neutron shield filled with water. The wood in the impact limiter effectively prevented thermal penetration, limiting the temperature rise of the inner cavity to only 13°C in test 4. The maximum temperature rise of the inner cavity surface, which occurred in test 3 with the neutron shield voided, was 80°C. These thermal data will be used to refine a transient thermal analytical model, which can then be utilized to predict the thermal response of other nuclear material shipping system designs subjected to torch fire environments.