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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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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Deep Space: The new frontier of radiation controls
In commercial nuclear power, there has always been a deliberate tension between the regulator and the utility owner. The regulator fundamentally exists to protect the worker, and the utility, to make a profit. It is a win-win balance.
From the U.S. nuclear industry has emerged a brilliantly successful occupational nuclear safety record—largely the result of an ALARA (as low as reasonably achievable) process that has driven exposure rates down to what only a decade ago would have been considered unthinkable. In the U.S. nuclear industry, the system has accomplished an excellent, nearly seamless process that succeeds to the benefit of both employee and utility owner.
Han Gon Kim, John C. Lee
Nuclear Science and Engineering | Volume 127 | Number 3 | November 1997 | Pages 300-316
Technical Paper | doi.org/10.13182/NSE97-A1937
Articles are hosted by Taylor and Francis Online.
A new critical heat flux (CHF) correlation has been developed by using the alternating conditional expectation (ACE) algorithm, which yields an optimal relationship between a dependent variable and multiple independent variables. In general, CHF correlation development requires tedious and time-consuming effort because it involves multivariate nonlinear regression analysis. For this reason, existing CHF correlations are usually applicable to specific, and often narrow, ranges of physical parameters. The ACE algorithm is applied to a collection of 12879 CHF data points for forced convective boiling in vertical tubes, and a generalized correlation covering a broad range of flow parameters is obtained. The mean, root mean square, and maximum errors of our new correlation are -0.558, 12.5, and 122.6%, respectively. Our CHF correlation represents the entire set of CHF data with an overall accuracy equivalent to or better than that of three existing correlations. Our results are particularly superior in the high-pressure region covering the rated conditions of pressurized water reactors, as well as in the low-pressure region.
