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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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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NRC begins special inspection at Hope Creek
The Nuclear Regulatory Commission is conducting a special inspection at Hope Creek nuclear plant in New Jersey to investigate the cause of repeated inoperability of one of the plant’s emergency diesel generators, the agency announced in a February 25 news release.
Mark W. Crump, John C. Lee
Nuclear Science and Engineering | Volume 77 | Number 2 | February 1981 | Pages 192-210
Technical Paper | doi.org/10.13182/NSE81-A21353
Articles are hosted by Taylor and Francis Online.
We present a new computational method developed for fluid flows, in which both compressibility and thermal expansion effects are important. Application of the method in transient thermal-hydraulic analysis of nuclear steam generators is also presented. The fluid model is based on one-dimensional, nonlinear, single-fluid conservation equations for mass, momentum, and energy. An empirical slip flow model is included to enable description of two-phase flows as well as single-phase flows. Numerical solution is based on the implicit continuous-fluid Eulerian (ICE) method, which provides stable numerical solutions for compressible fluid flows. An extension of this method (designated as the EICE method) is developed to account for thermal expansion effects. This is achieved by including implicit energy dependence in coupled equations of mass, momentum, and state, and solving the full system of fluid equations through a two-step iterative technique. The development of the EICE method is presented and discussed, along with specific calculations for once-through and U-tube steam generator transients, natural flow oscillations, and a vessel blowdown transient.