References
- Letzring , W. J. 1977 . BWR blowdown/emergency core cooling program; Preliminary facility description report for the BD/ECC1A test phase . GEAP-23592 ,
- Lee , L. S. and Sozzi , G. L. Aug. 1981 . Thermal-hydraulic responses in the scaled BWR system simulator during a design basis accident simulation tests Paper presented at the 20th National Heat Transfer Conference, Milwaukee, Wisconsin
- Anoda , Y. 1980 . ROSA-III system description . JAERI-M , 9243
- Soda , K. 1983 . Boiling water loss of coolant tests; Single failbre tests with ROSA-III . J. Nucl. Sci. Technol. , 20 ( 7 ) : 537 – 558 .
- Piggott , W. D. G. and Ackerman , M. C. 1982 . “ A study of countercurrent flow and flooding in parallel channels ” . In “Heat Transfer in Nuclear Reactor Safety” Edited by: Bankoff , S. G. and Afgan , N. H. 361 – 377 . Washington D. C. : Hemisphere Publ. .
- Wallis , G. B. 1981 . Countercurrent gas-liquid flow in parallel vertical tubes . Int. J. Multiphase Flow , 7 : 1 – 19 .
- Findlay , J. A. 1982 . BWR refill/reflood program task 4.4; CCFL/refill system effect tests (30° Sector); Evaluation of parallel channel phanomena . NUREG/CR-2566 ,
- Conlon , W. M. and Lahey , R. T. 1982 . An experimental investigation of boiling water nuclear reactor parallel channel effects during a postulated loss-of-collant accident . NUREG/CR-2971 ,
- Murase , M. and Naitoh , M. 1985 . BWR loss of coolant integral tests with the two bundle loop, (I), Thermal-hydraulic characteristics in parallel channels . J. Nucl. Sci. Technol. , 22 ( 3 ) : 213
- The Tokyo Electric Power Co. May 1982 . “ Fukushima 2nd Nuclear Power Station; ” . In Report for Construction Permit, (in Japanese)
- ANS proposed standard . Oct. 1973 . Decay energy release rate following shutdown of uranium-fueled thermal reactors, ANS 5.1 Rev
- Nucl. Safety Bureau of Sci., Technol. Agency . 1981 . “Guidelines for Construction Permit of Nuclear Safety Commission”, (in Japanese) 349 – 351 . Taishei-Shuppan-Sha. .