CANDU 3 transient analysis using Atomic Energy of Canada Ltd. codes

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Description

A limited number of transient scenarios were calculated using a computer code suite and input modeling provided by the Atomic Energy of Canada Limited (AECL) for the CANDU 3 design. Emphasis was placed on a large-break loss-of-coolant accident with delays in actuation of the two independent shutdown systems (shutdown rods and liquid poison injection). Although an extremely unlikely scenario, it was studied because of the potential consequences that would result from a positive void coefficient of reactivity. Results indicate that a few seconds delay in shutdown would result in quickly reaching fuel or cladding melting temperatures before the emergency core ... continued below

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72 p.

Creation Information

Judd, J.L.; Shumway, R.W. & Ebert, D.D. January 1, 1995.

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  • Judd, J.L.
  • Shumway, R.W. Lockheed Idaho Technologies Co., Idaho Falls, ID (United States)
  • Ebert, D.D. Nuclear Regulatory Commission, Washington, DC (United States). Div. of Systems Technology

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Description

A limited number of transient scenarios were calculated using a computer code suite and input modeling provided by the Atomic Energy of Canada Limited (AECL) for the CANDU 3 design. Emphasis was placed on a large-break loss-of-coolant accident with delays in actuation of the two independent shutdown systems (shutdown rods and liquid poison injection). Although an extremely unlikely scenario, it was studied because of the potential consequences that would result from a positive void coefficient of reactivity. Results indicate that a few seconds delay in shutdown would result in quickly reaching fuel or cladding melting temperatures before the emergency core cooling system would be activated. Only small changes in the timing and consequences of the scenario result when several parameters, of potential importance to the progression of the accident, are varied. Five calculations were also performed for loss-of-off-site-power scenarios. These calculations assume that the plant failed to enter the island mode, i.e., power to the main coolant pumps was not restored using on-site power generation.

Physical Description

72 p.

Notes

INIS; OSTI as TI95008325

Source

  • Other Information: PBD: Jan 1995

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Identifier

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  • Other: TI95008325
  • Report No.: NUREG/CR--6257
  • Report No.: INEL--95/0070
  • DOI: 10.2172/31699 | External Link
  • Office of Scientific & Technical Information Report Number: 31699
  • Archival Resource Key: ark:/67531/metadc679096

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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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Creation Date

  • January 1, 1995

Added to The UNT Digital Library

  • July 25, 2015, 2:20 a.m.

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  • June 25, 2018, 5:11 p.m.

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Judd, J.L.; Shumway, R.W. & Ebert, D.D. CANDU 3 transient analysis using Atomic Energy of Canada Ltd. codes, report, January 1, 1995; Washington D.C.. (digital.library.unt.edu/ark:/67531/metadc679096/: accessed December 15, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.