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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.
Meeting Spotlight
2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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!
Latest Magazine Issues
Sep 2024
Jan 2024
Latest Journal Issues
Nuclear Science and Engineering
November 2024
Nuclear Technology
October 2024
Fusion Science and Technology
Latest News
Constellation announces TMI-1 restart, power purchase agreement with Microsoft
Nuclear powerhouse Constellation announced today the signing of a 20-year power purchase agreement with Microsoft that will pave the way for the restart of Three Mile Island Unit 1—under a new name to honor Chris Crane, former chief executive of Constellation’s parent company, Exelon, who passed away earlier this year.
David Garrido (ENSA), Steven Ross (PNNL), Paul E. McConnell, Willaim Uncapher (SNL), Philip Jensen, Nicholas Klymyshyn (PNNL), Sylvia Saltzstein, Ken Sorenson (SNL), Brady Hanson, Ralph Best (PNNL), William Shust (Objective Engineers), Jeff L. England (SRNS), Russ Walker, Ruben Pena (Transportation Technology Center, Inc.)
Proceedings | 16th International High-Level Radioactive Waste Management Conference (IHLRWM 2017) | Charlotte, NC, April 9-13, 2017 | Pages 72-78
The objective of the shock and vibration testing program is to quantify mechanical loads on fuel assembly components that would occur during normal conditions of transportation (NCT) by various modes. This information will guide materials research and establish a technical basis for review organizations such as the U.S. Nuclear Regulatory Commission (NRC). A significant body of experimental and numerical modeling data exists to quantify loads and failure limits applicable to NCT rail transport, but the data are either out-of-date relative to present day railroad operations and equipment, or are based on assumptions that can only be verified through experimental testing. The summary presented herein represents a collaboration among many stakeholders to define the path for acquiring new data that is needed to validate the assumptions of previous work, validate modelling methods that will be needed to evaluate the mechanical responses of used nuclear fuel that will be transported in the future in large rail casks, and inform material test campaigns on the anticipated range of stresses that will be imposed on nuclear fuel cladding. This work will include full scale testing of a used nuclear fuel cask, cradle, rail car, and surrogate fuel assemblies and will encompass intermodal transloading, heavy-haul truck transport, barge transport, ocean going vessel transport, and rail transport as well as captive track tests. The ultimate goal of this testing will be to close some of the existing knowledge gaps related to the mechanical loads that would be imposed on used nuclear fuel under NCT and inform the experiments and analysis efforts