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Nuclear Technology Volume 132, 2000 - Issue 1: Special on Accelerator Applications
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Technical Paper

Analysis of an Advanced Test Reactor Small-Break Loss-of-Coolant Accident with an Engineered Safety Feature to Automatically Trip the Primary Coolant Pumps

Steven T. PolkinghorneIdaho National Engineering and Environmental Laboratory Bechtel BWXT Idaho, LLC, P.O. Box 1625, Idaho Falls, Idaho 83415
,
Cliff B. DavisIdaho National Engineering and Environmental Laboratory Bechtel BWXT Idaho, LLC, P.O. Box 1625, Idaho Falls, Idaho 83415
&
Richard T. McCrackenIdaho National Engineering and Environmental Laboratory Bechtel BWXT Idaho, LLC, P.O. Box 1625, Idaho Falls, Idaho 83415
Pages 167-178 | Published online: 13 May 2017

References

  • “Advanced Test Reactor Upgraded Final Safety Analysis Report,” Rev. 1999, AU, Bechtel BWXT Idaho (July 1999).
  • “SCDAP/RELAP5/MOD2 Code Manual, Vols. 1, 2, and 3,” NUREG/CR-5273, EGG-2555, C. M. ALLISON and E. C. JOHNSON, Eds., EG&G Idaho (Sep. 1989).
  • J. D. GASKI, “SINDA 1987/ANSI Computer Code,” Network Analysis Associates (Oct. 1987).
  • C. B. DAVIS, “Pump Cavitation in Savannah River Reactors During Loss-of-Coolant Accidents,” Nucl. Technol., 90, 286 (June 1990).
  • V. H. RANSOM, R. J. WAGNER, and G. W. JOHNSEN, “RELAP5/MOD2 Code Manual, Vol. 3: Developmental Assessment Problems,” EGG-TFM-7952, EG&G Idaho (Dec. 1987).
  • S. T. POLKINGHORNE, “Validation of the ATR-SINDA Fuel Plate Model Using Advanced Test Reactor Startup Data,” Nucl. Technol., 108, 395 (Dec. 1994).
  • C. J. PFEIFER, “PDQ-7 Reference Manual II,” WAPD-TM-947 (L), Westinghouse Electric Corporation (Feb. 1971).
  • M. W. CROFT, “Advanced Test Reactor Burnout Heat Transfer Tests,” IDO-24465, U.S. Atomic Energy Commission (Jan. 1964).
  • E. D. WATERS, “Heat Transfer Experiments for the Advanced Test Reactor,” BNWL-216, Battelle Northwest Laboratory (May 1966).

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