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).