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Journal of Nuclear Science and Technology Volume 20, 1983 - Issue 7
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Original Paper

Boiling Water Reactor Loss of Coolant Tests Single Failure Tests with ROSA-III

Kunihisa SODA Division of Reactor Safety, Japan Atomic Energy Research Institute, Tokai-mura, Ibaraki-ken, 319-11
,
Kanji TASAKA Division of Reactor Safety, Japan Atomic Energy Research Institute, Tokai-mura, Ibaraki-ken, 319-11
,
Nobuaki ABE Division of Reactor Safety, Japan Atomic Energy Research Institute, Tokai-mura, Ibaraki-ken, 319-11
&
Masayoshi SHIBA Division of Reactor Safety, Japan Atomic Energy Research Institute, Tokai-mura, Ibaraki-ken, 319-11
Pages 537-558 | Received 02 Nov 1981, Published online: 15 Mar 2012

REFERENCES

  • Nuclear Safety Commission . 1978 . Safety evaluation criteria for a light water nuclear power plant, (in Japanese
  • Shimamune , H. 1974 . “ Thermohydraulic behavior in a primary cooling system during a loss-of-coolant accident of a light water reactor (Results of the mock-up test with ROSA-I) ” . In JAERI-M6318, (in Japanese)
  • Adachi , H. 1982 . ROSA-II experimental program for PWR LOCA/ECCS integral tests . JAERI-1277 ,
  • Tasaka , K. and Shiba , M. 1980 . “ ROSA-III program at JAERI for BWR/LOCA/ECCS integral tests ” . In Proc. ANS/ENS Topical Meeting on Thermal Reactor Safety, Apr. 6–9, 1980, Knoxville, Tennessee, USA 427 – 435 .
  • Soda , K. , Tasaka , K. and Shiba , M. 1980 . Boiling water reactor LOCA/ECCS integral tests at ROSA-III facility of JAERI 1 – 5 . Yugoslavia : Dubrovnik . Presented at Int. Seminar on Nuclear Reactor Safety Heat Transfer, Sep
  • Anoda , Y. 1980 . ROSA-III system description . JAERI-M , 9243
  • Sobajima , M. 1979 . “ Instrumentation and data processing method of the ROSA-III test ” . In JAERI-M8449, (in Japanese)
  • Abe , N. and Tasaka , K. 1980 . Electric power transient curve for ROSA-III tests . JAERI-M , 8728 (in Japanese
  • EG & G, Idaho Inc. 1978 . EG & G Rep. CDAP-TR-003 , RELAP4/Mod 6, A computer program for transient thermal hydraulic analysis of nuclear reactors and related systems, User's manual
  • Wilson , J. F. 1961 . The velocity of rising steam in a bubbling two-phase mixture . Trans. Am. Nucl. Soc. , 4 : 356
  • Henry , R. E. 1971 . The two-phase critical flow of one component mixtures in nozzles, orifices and short tubes . J. Heat Transfer , 93 : 179
  • Hutcherson , M. N. 1975 . “ Contribution to the theory of the two-phase blowdown phenomenon ” . In ANL/RAS 75 – 42 .

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