Fracture probability and leak before break analysis for the cold neutron source moderator vessel

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Fracture mechanics calculations are made to ensure the safety of the moderator vessel against failure by fracture. The 6061-T6 aluminum alloy is used for the moderator vessel structure. The fracture analysis of the moderator vessel consists of: (1) the probability of fracture calculations at the locations of the moderator where either the primary stress or the secondary stress assumes the highest value, (2) the vessel wall leak-before-break analysis by applying an edge crack solution, and (3) the crack penetration calculation as a result of radiation embrittlement by applying the flaw assessment diagram (FAD). The probability of fracture for the capsule ... continued below

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13 p.

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Chang, S.J. April 1, 1998.

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Description

Fracture mechanics calculations are made to ensure the safety of the moderator vessel against failure by fracture. The 6061-T6 aluminum alloy is used for the moderator vessel structure. The fracture analysis of the moderator vessel consists of: (1) the probability of fracture calculations at the locations of the moderator where either the primary stress or the secondary stress assumes the highest value, (2) the vessel wall leak-before-break analysis by applying an edge crack solution, and (3) the crack penetration calculation as a result of radiation embrittlement by applying the flaw assessment diagram (FAD). The probability of fracture for the capsule is calculated by using a direct probability integration method instead of the Monte Carlo simulation method used by the PRAISE Code or the FAVOR Code developed in Oak Ridge. The probability of fracture as a function of radiation embrittlement is obtained. The leak before break analysis indicates that the vessel will fail by leak before fail by catastrophic fracture. A mass spectrometer will be installed to monitor the leak of hydrogen circulating within the moderator.

Physical Description

13 p.

Notes

INIS; OSTI as DE98005653

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  • 1998 ASME/JSME joint pressure vessel and piping (PVP) conference, San Diego, CA (United States), 26-30 Jul 1998

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  • Other: DE98005653
  • Report No.: ORNL/CP--98192
  • Report No.: CONF-980708--
  • Grant Number: AC05-96OR22464
  • Office of Scientific & Technical Information Report Number: 672057
  • Archival Resource Key: ark:/67531/metadc709592

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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.

Office of Scientific and Technical Information (OSTI) is the Department of Energy (DOE) office that collects, preserves, and disseminates DOE-sponsored research and development (R&D) results that are the outcomes of R&D projects or other funded activities at DOE labs and facilities nationwide and grantees at universities and other institutions.

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  • April 1, 1998

Added to The UNT Digital Library

  • Sept. 12, 2015, 6:31 a.m.

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  • Jan. 19, 2016, 1:51 p.m.

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Chang, S.J. Fracture probability and leak before break analysis for the cold neutron source moderator vessel, article, April 1, 1998; Tennessee. (digital.library.unt.edu/ark:/67531/metadc709592/: accessed September 25, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.