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

Experimental Study of Upper Core Quench in PWR Reflood Phase

Yutaka ABE Japan Atomic Energy Research Institute, Tokai-mura, Ibaraki-ken, 319-11
,
Yukio SUDO Japan Atomic Energy Research Institute, Tokai-mura, Ibaraki-ken, 319-11
&
Masahiro OSAKABE Japan Atomic Energy Research Institute, Tokai-mura, Ibaraki-ken, 319-11
Pages 571-583 | Received 02 Feb 1983, Published online: 15 Mar 2012

REFERENCES

  • TRAC-PD2 . 1981 . LA-8709-MS, NUREG/CR-2054 , An advanced best-estimate computer program for pressurized water reactor loss-of-coolant accident analysis
  • RELAP4/Mod6 . 1979 . EY-76-C-07–1570 , A computer program for transient thermal-hydraulic analysis of nuclear reactors and related systems
  • Sudo , Y. 1982 . Analysis of TRAC and SCTF results for system pressure-effect tests under forced flooding . LA-9258-MS, NUREG/CR-2622 ,
  • Yamanouchi , A. 1968 . Effect of core spray cooling in transient start after loss of coolant accident . J. Nucl. Sci. Technol. , 5 ( 11 ) : 547 – 558 .
  • Duffey , R. B. and Porthouse , D. T. C. 1973 . The physics of rewetting in water reactor emergency core cooling . Nucl. Eng. Design , 25 : 379 – 394 .
  • Tompson , T. S. 1975 . “ Rewetting of a hot surface ” . In AECL-5060 139 – 143 .
  • Murao , Y. 1978 . Correlation of quench phenomena for bottom flooding during loss-of-coolant accident . J. Nucl. Sci. Technol , 15 ( 12 ) : 875 – 885 .
  • Cermak , J. O. 1970 . PWR full length emergency cooling heat transfer (FLECHT) group I test report
  • Adachi , H. 1982 . “ SCTF core-I test results (System pressure effects on reflooding phenomena) ” . In JAERI-M 82 – 075 .

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