Development of GAMMA Code and Evaluation for a Very High Temperature gas-Cooled Reactor

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The very high-temperature gas-cooled reactor (VHTR) is envisioned as a single- or dual-purpose reactor for electricity and hydrogen generation. The concept has average coolant temperatures above 9000C and operational fuel temperatures above 12500C. The concept provides the potential for increased energy conversion efficiency and for high-temperature process heat application in addition to power generation. While all the High Temperature Gas Cooled Reactor (HTGR) concepts have sufficiently high temperature to support process heat applications, such as coal gasification, desalination or cogenerative processes, the VHTR’s higher temperatures allow broader applications, including thermochemical hydrogen production. However, the very high temperatures of this reactor ... continued below

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Oh, Chang H; Lim, H.S.; Kim, E.S. & NO, H.C. June 1, 2007.

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The very high-temperature gas-cooled reactor (VHTR) is envisioned as a single- or dual-purpose reactor for electricity and hydrogen generation. The concept has average coolant temperatures above 9000C and operational fuel temperatures above 12500C. The concept provides the potential for increased energy conversion efficiency and for high-temperature process heat application in addition to power generation. While all the High Temperature Gas Cooled Reactor (HTGR) concepts have sufficiently high temperature to support process heat applications, such as coal gasification, desalination or cogenerative processes, the VHTR’s higher temperatures allow broader applications, including thermochemical hydrogen production. However, the very high temperatures of this reactor concept can be detrimental to safety if a loss-of-coolant accident (LOCA) occurs. Following the loss of coolant through the break and coolant depressurization, air will enter the core through the break by molecular diffusion and ultimately by natural convection, leading to oxidation of the in-core graphite structure and fuel. The oxidation will accelerate heatup of the reactor core and the release of toxic gasses (CO and CO2) and fission products. Thus, without any effective countermeasures, a pipe break may lead to significant fuel damage and fission product release. Prior to the start of this Korean/United States collaboration, no computer codes were available that had been sufficiently developed and validated to reliably simulate a LOCA in the VHTR. Therefore, we have worked for the past three years on developing and validating advanced computational methods for simulating LOCAs in a VHTR. This paper will also include what improvements will be made in the Gamma code for the VHTR.

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  • ANS Meeting,Boston,06/24/2007,06/28/2007

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  • Report No.: INL/CON-06-12033
  • Grant Number: DE-AC07-99ID-13727
  • Office of Scientific & Technical Information Report Number: 912894
  • Archival Resource Key: ark:/67531/metadc890171

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Office of Scientific & Technical Information Technical Reports

Reports, articles and other documents harvested from the Office of Scientific and Technical Information.

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  • June 1, 2007

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  • Sept. 22, 2016, 2:13 a.m.

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  • Nov. 7, 2016, 5:25 p.m.

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Oh, Chang H; Lim, H.S.; Kim, E.S. & NO, H.C. Development of GAMMA Code and Evaluation for a Very High Temperature gas-Cooled Reactor, article, June 1, 2007; [Idaho Falls, Idaho]. (digital.library.unt.edu/ark:/67531/metadc890171/: accessed October 24, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.