TRAC L reactor model: Geometry review and benchmarking

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Description

The analysis of the Design Basis Loss of Coolant Acident (LOCA) for Savannah River Site (SRS) reactors involves the best estimate reactor system thermal-hydraulics code TRAC-PFI/MOD1. Power levels for the L-3.1 and P-10.2 subcycles were determined based, in part, on TRAC analyses of the first few seconds of a plenum inlet break LOCA. The TRAC code is currently being used to analyze reactor system response for the Double Ended Guillotine Break (DEGB) LOCA, the Expansion Joint Bellows Break LOCA, the Loss of Pumping Accident (LOPA), and the Pump Shaft Break event. Currently, the DEGB LOCA analysis is performed with TRAC ... continued below

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Pages: (79 p)

Creation Information

Griggs, D.P. (Westinghouse Savannah River Co., Aiken, SC (United States)) & Cozzuol, J.M. (Idaho National Engineering Lab., Idaho Falls, ID (United States)) August 1, 1990.

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Description

The analysis of the Design Basis Loss of Coolant Acident (LOCA) for Savannah River Site (SRS) reactors involves the best estimate reactor system thermal-hydraulics code TRAC-PFI/MOD1. Power levels for the L-3.1 and P-10.2 subcycles were determined based, in part, on TRAC analyses of the first few seconds of a plenum inlet break LOCA. The TRAC code is currently being used to analyze reactor system response for the Double Ended Guillotine Break (DEGB) LOCA, the Expansion Joint Bellows Break LOCA, the Loss of Pumping Accident (LOPA), and the Pump Shaft Break event. Currently, the DEGB LOCA analysis is performed with TRAC only for the flow instability (FI) phase of the accident. This analysis provides input to the determination of operating power limits for the K-14.1 subcycle.

Physical Description

Pages: (79 p)

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OSTI; NTIS; INIS; GPO Dep.

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  • Other: DE92016494
  • Report No.: WSRC-TR-90-32
  • Grant Number: AC09-89SR18035
  • DOI: 10.2172/5059159 | External Link
  • Office of Scientific & Technical Information Report Number: 5059159
  • Archival Resource Key: ark:/67531/metadc1058123

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Creation Date

  • August 1, 1990

Added to The UNT Digital Library

  • Jan. 22, 2018, 7:23 a.m.

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  • Feb. 1, 2018, 7:11 p.m.

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Griggs, D.P. (Westinghouse Savannah River Co., Aiken, SC (United States)) & Cozzuol, J.M. (Idaho National Engineering Lab., Idaho Falls, ID (United States)). TRAC L reactor model: Geometry review and benchmarking, report, August 1, 1990; Aiken, South Carolina. (digital.library.unt.edu/ark:/67531/metadc1058123/: accessed April 20, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.