Preliminary probabilistic design accident evaluation of the cold source facilities of the advanced neutron source

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Consistent with established Advanced Neutron Source (ANS) project policy for the use of probabilistic risk assessment (PRA) in design, a task has been established to use PRA techniques to help guide the design and safety analysis of the ANS cold sources. The work discussed in this report is the first formal output of the cold source PRA task. The major output at this stage is a list of design basis accidents, categorized into approximate frequency categories. This output is expected to focus attention on continued design work to define and optimize the design such that design basis accidents are better ... continued below

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42 p.

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Harrington, R. M. & Ramsey, C. T. August 1, 1995.

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Description

Consistent with established Advanced Neutron Source (ANS) project policy for the use of probabilistic risk assessment (PRA) in design, a task has been established to use PRA techniques to help guide the design and safety analysis of the ANS cold sources. The work discussed in this report is the first formal output of the cold source PRA task. The major output at this stage is a list of design basis accidents, categorized into approximate frequency categories. This output is expected to focus attention on continued design work to define and optimize the design such that design basis accidents are better defined and have acceptable outcomes. Categorizing the design basis events (DBEs) into frequency categories should prove helpful because it will allow appropriate acceptance criteria to be applied. Because the design of the cold source is still proceeding, it is beyond the scope of this task to produce detailed event probability calculations or even, in some cases, detailed event sequence definitions. That work would take place as a logically planned follow-on task, to be completed as the design matures. Figure 1.1 illustrates the steps that would typically be followed in selecting design basis accidents with the help of PRA. Only those steps located above the dashed line on Fig. 1.1 are included in the scope of the present task. (Only an informal top-level failure modes and effects analysis was done.) With ANS project closeout expected in the near future, the scope of this task has been abbreviated somewhat beyond the state of available design information on the ANS cold sources, or what could be achieved in a reasonable time. This change was necessary to ensure completion before the closeout and because the in-depth analytical support necessary to define fully some of the accidents has already been curtailed.

Physical Description

42 p.

Notes

INIS; OSTI as DE96006460

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  • Other Information: PBD: Aug 1995

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  • Other: DE96006460
  • Report No.: ORNL/M--4606
  • Grant Number: AC05-84OR21400
  • DOI: 10.2172/204247 | External Link
  • Office of Scientific & Technical Information Report Number: 204247
  • Archival Resource Key: ark:/67531/metadc666141

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Office of Scientific & Technical Information Technical Reports

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Creation Date

  • August 1, 1995

Added to The UNT Digital Library

  • June 29, 2015, 9:42 p.m.

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  • March 6, 2017, 4:04 p.m.

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Harrington, R. M. & Ramsey, C. T. Preliminary probabilistic design accident evaluation of the cold source facilities of the advanced neutron source, report, August 1, 1995; Tennessee. (digital.library.unt.edu/ark:/67531/metadc666141/: accessed October 23, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.