References
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- J. D. GASKI, “SINDA 1987/ANSI Computer Code,” Network Analysis Associates (Oct. 1987).
- “Safety Analysis Report for the Advanced Test Reactor,” SAR-153, Rev. 11 (Feb. 2003).
- S. T. POLKINGHORNE, C. B. DAVIS, and R. T. McCRACKEN, “Analysis of an Advanced Test Reactor SmallBreak Loss-of-Coolant Accident with an Engineered Safety Feature to Automatically Trip the Primary Coolant Pumps,” Nucl. Technol, 132, 167 (2000).
- S. T. POLKINGHORNE, “Validation of the ATR-SINDA Fuel Plate Model Using Advanced Test Reactor Startup Data,” Nucl. Technol, 108, 395 (1994).
- C. J. PFEIFER, “PDQ-7 Reference Manual II,” WAPD-TM-947(L), Westinghouse Electric (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 Laboratories (May 1966).