Modeling a Helical-coil Steam Generator in RELAP5-3D for the Next Generation Nuclear Plant

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Options for the primary heat transport loop heat exchangers for the Next Generation Nuclear Plant are currently being evaluated. A helical-coil steam generator is one heat exchanger design under consideration. Safety is an integral part of the helical-coil steam generator evaluation. Transient analysis plays a key role in evaluation of the steam generators safety. Using RELAP5-3D to model the helical-coil steam generator, a loss of pressure in the primary side of the steam generator is simulated. This report details the development of the steam generator model, the loss of pressure transient, and the response of the steam generator primary and ... continued below

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Hoffer, Nathan V.; Sabharwall, Piyush & Anderson, Nolan A. January 1, 2011.

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This report is part of the collection entitled: Office of Scientific & Technical Information Technical Reports and was provided by UNT Libraries Government Documents Department to Digital Library, a digital repository hosted by the UNT Libraries. It has been viewed 222 times , with 13 in the last month . More information about this report can be viewed below.

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Options for the primary heat transport loop heat exchangers for the Next Generation Nuclear Plant are currently being evaluated. A helical-coil steam generator is one heat exchanger design under consideration. Safety is an integral part of the helical-coil steam generator evaluation. Transient analysis plays a key role in evaluation of the steam generators safety. Using RELAP5-3D to model the helical-coil steam generator, a loss of pressure in the primary side of the steam generator is simulated. This report details the development of the steam generator model, the loss of pressure transient, and the response of the steam generator primary and secondary systems to the loss of primary pressure. Back ground on High Temperature Gas-cooled reactors, steam generators, the Next Generation Nuclear Plant is provided to increase the readers understanding of the material presented.

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  • Report No.: INL/EXT-10-19621
  • Grant Number: DE-AC07-05ID14517
  • DOI: 10.2172/1004263 | External Link
  • Office of Scientific & Technical Information Report Number: 1004263
  • Archival Resource Key: ark:/67531/metadc832462

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Office of Scientific & Technical Information Technical Reports

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  • January 1, 2011

Added to The UNT Digital Library

  • May 19, 2016, 3:16 p.m.

Description Last Updated

  • June 20, 2016, 3:43 p.m.

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Hoffer, Nathan V.; Sabharwall, Piyush & Anderson, Nolan A. Modeling a Helical-coil Steam Generator in RELAP5-3D for the Next Generation Nuclear Plant, report, January 1, 2011; Idaho Falls, Idaho. (https://digital.library.unt.edu/ark:/67531/metadc832462/: accessed May 26, 2019), University of North Texas Libraries, Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.