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Division Spotlight
Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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
First GAIN vouchers of 2025 go to Curio, Deep Fission, Kairos, and NuCube Energy
The Department of Energy’s Gateway for Accelerated Innovation in Nuclear (GAIN) has awarded four fiscal year 2025 vouchers to support the development of advanced nuclear technologies. Each company will get access to specific capabilities and expertise in the DOE’s national laboratory complex—in this round of awards both Idaho National Laboratory and Pacific Northwest National Laboratory are named—and will be responsible for a minimum 20 percent cost share, which can be an in-kind contribution.
Eberhard Alstadt, Frank-Peter Weiss
Nuclear Technology | Volume 128 | Number 1 | October 1999 | Pages 46-57
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT99-A3013
Articles are hosted by Taylor and Francis Online.
A finite element model describing the mechanical vibrations of the whole WWER-440 primary circuit was established to support the early detection of mechanical component faults. A special fluid-structure module was developed to consider the reaction forces of the fluid in the downcomer upon the moving core barrel and the reactor pressure vessel (RPV). This fluid-structure interaction (FSI) module is based on an approximated analytical two-dimensional solution of the coupled system of three-dimensional fluid equations and the structural equations of motions. By means of the vibration model, all eigenfrequencies up to 30 Hz and the corresponding mode shapes were calculated. It is shown that the FSI strongly influences those modes that lead to a relative displacement between the RPV and the core barrel. Moreover, by means of the model, the shift of eigenfrequencies due to the degradation or to the failure of internal clamping and spring elements was investigated. Comparing the frequency spectra of the normal and the faulty structure, one could prove that recognizing such degradations and failures even inside the RPV is possible by pure ex-core vibration measurements.