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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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New coolants, new fuels: A new generation of university reactors
Here’s an easy way to make aging U.S. power reactors look relatively youthful: Compare them (average age: 43) with the nation’s university research reactors. The 25 operating today have been licensed for an average of about 58 years.
Joseph A. Naser
Nuclear Technology | Volume 54 | Number 3 | September 1981 | Pages 373-379
First International Retran Meeting | Heat Transfer and Fluid Flow | doi.org/10.13182/NT81-A32782
Articles are hosted by Taylor and Francis Online.
The RETRAN system thermal-hydraulics analysis code has been used to simulate the three turbine trip tests at the Peach Bottom Unit 2 boiling water reactor. The latest analysis used the dynamic slip, profile fit subcooled void, and point kinetics models in RETRAN-02. The results demonstrated that RETRAN is capable of simulating operational transients such as turbine trips. The analysis aided in understanding physical phenomena not well known such as the transient behavior of the steam bypass system and the pressure vessel. Experience gained in this work pointed out the importance of having good experimental data for code qualification purposes. This includes knowing the initial conditions, boundary conditions, control system and equipment parameters, and operator actions. The analysis of these three tests will be repeated in the future using one-dimensional kinetics, improved steam separator, and mechanistic subcooled voiding models.