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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.
Hongdong Zhen, Songtao Yin, Lei Zhang, Ningning Wang, Bo Xu, Haijun Wang
Nuclear Technology | Volume 207 | Number 1 | January 2021 | Pages 54-61
Technical Paper | doi.org/10.1080/00295450.2020.1739994
Articles are hosted by Taylor and Francis Online.
This paper aims to revise the critical flow criterion and flashing inception of the analytical critical flow model and to further explore the effect of upstream conditions on critical mass fluxes. The flashing inception of the model is considered to be affected by the Reynolds number and the Jakob number. Model predictions show strong similarities with test results compared with other models, with average errors of less than 10.1% for simulated slits and 15.8% for natural cracks. Upstream parameters of the liquid, such as the stagnation pressure, subcooling, and aspect ratio, directly influence the rate of depressurization, the thermodynamic nonequilibrium constant, and the friction pressure drop, respectively, which determine the critical mass flux. This research provides the theoretical basis for accurate assessment of critical crack, providing safeguards for monitoring nuclear reactor leaks.