Analysis of capsule HFR-B1 graphite-corrosion data

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The recently completed irradiation of capsule HFR-B1 in the high-flux reactor at the Pitten Establishment in The Netherlands provided some excellent data for fission-product release. The data were obtained under irradiation and temperature conditions close to those expected during normal operation of the Modular High-Temperature Gas-cooled Reactor (MHTGR). Some of the tests at Petten were designed to measure release of fission gases during hydrolysis of failed fuel. Hydrolysis was initiated by injecting known amounts of water vapor into the capsule sweep gas. The measured concentrations of CO and CO{sub 2} in the capsule sweep gas indicated that a non-negligible amount ... continued below

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Medium: P; Size: 60 p. pages

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Richards, M.B. & Gillespie, A.G. January 1, 1991.

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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 17 times . More information about this report can be viewed below.

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  • General Atomic Company
    Publisher Info: General Atomics, San Diego, CA (United States)
    Place of Publication: San Diego, California

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Description

The recently completed irradiation of capsule HFR-B1 in the high-flux reactor at the Pitten Establishment in The Netherlands provided some excellent data for fission-product release. The data were obtained under irradiation and temperature conditions close to those expected during normal operation of the Modular High-Temperature Gas-cooled Reactor (MHTGR). Some of the tests at Petten were designed to measure release of fission gases during hydrolysis of failed fuel. Hydrolysis was initiated by injecting known amounts of water vapor into the capsule sweep gas. The measured concentrations of CO and CO{sub 2} in the capsule sweep gas indicated that a non-negligible amount of graphite corrosion was also occurring during the hydrolysis tests. Hence, these measurements provide some unique data for in-pile corrosion of grade H-4541 graphite by steam. In the present report, an analysis of graphite corrosion during the Petten hydrolysis tests is described. The calculations were performed using the REACT program, which is based on an improved corrosion model. The REACT program was developed as part of a research program at the University of California, San Diego, and is in operational status in the General Atomics (GA) Production Code Library. Predictions obtained with REACT show excellent agreement with the Petten graphite-corrosion data. This good agreement indicates that the currently used correlation for the steam-graphite reaction rate, which was obtained from out-of-pile measurements, may also be used to predict in-pile corrosion with good accuracy. 8 refs., 19 figs., 2 tabs.

Physical Description

Medium: P; Size: 60 p. pages

Notes

OSTI as DE00714916

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  • Other Information: PBD: 1 Jan 1991

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  • Report No.: DOE/HTGR--88510
  • Grant Number: AC03-89SF17885
  • DOI: 10.2172/714916 | External Link
  • Office of Scientific & Technical Information Report Number: 714916
  • Archival Resource Key: ark:/67531/metadc702823

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  • January 1, 1991

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  • Sept. 12, 2015, 6:31 a.m.

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  • April 18, 2016, 5:56 p.m.

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Richards, M.B. & Gillespie, A.G. Analysis of capsule HFR-B1 graphite-corrosion data, report, January 1, 1991; San Diego, California. (digital.library.unt.edu/ark:/67531/metadc702823/: accessed September 26, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.