ML20209A634

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Forwards marked-up Draft Mccauley Paper for Review Prior to Publication
ML20209A634
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Issue date: 08/09/1980
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FOIA-85-782 NUDOCS 8702030406
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UNITE 3 STATES NUCLEAR RESULATORY COMMisslON

[ WASHINGTON,0.C. 20655 Vent full-Scale

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the wetwell loading

,g' eactor (BWR) Containment in Atomic Energy Research

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azW nt (LOCA) conditions.

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, Iram for the Mark II BWR

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[ 9/gg'c> iulatory Connission j, c o [M n assessing and correlating the JAERI data to develop a confirmatory data base for use in the licensingofU.S.MarkIInuclearpowerplants[andinthedevelopmentof N advanced containment code The JAERI tests represent the sole source of l McD \ -V A full-scale Mark I data available, amtarT%erWe :f ;;r;;t '-te-+ in 7 l riode, "k;:n$; pr;;;;s.

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,j/ Containment Response in the JAERI Multivent Full-Scale 1

Mark II Pressure Suppression Experiments

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K. Namatame, Y. Kukita, and M. Shiba E. W. McCauley and G. S. Holman Japan Atomic Energy Research Institute Lawrence Livermore National Laboratory Tokai-Mura, Japan Livermore, California, U.S. A.

Submitted to the 6th International Conference on Structural Mechanics in Reactor Technology August 17 - 21, 1981 Paris, France RDfV iSU$ MARY-,  ;

This report presents definitive information regarding the wetwell loading conditions in the full-scale multivent boiling water reactor (BWR) Containment Response Tests (CRT) currently in progress at the Japan Atomic Energy Research Institute (JAERI). These tests focus on hydrodynamic loads induced'in a unique full-scale,1/18-volume replica of a General Electric Mark II BWR

( containment system by simulated loss of coolant accident (LOCA) conditions.

JAERI, in coordination with interested agencies in Japan and the United States, was comissioned in 1978 to develop a test program for the Mark II BWR containment. The Lawrence Livermore National Laboratory (LLNL) acts as the liaison between JAERI and the United States, Nuclear Regulatory Commission (U.S. NRC) for this program, with particular emphasis on assessing and l

l correlating the JAERI data to develop a confirmatory data base for use in the j l licensingofU.S.MarkIInuclearpowerplants[andinthedevelopmentof /

  • advanced containment code The JAERI tests represent the sole source of

%%D \ -V IM7 full-scale Mark II data available, and are ttierak-e :f gut +h?

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Of a total of 36 planned tests, 14 have been c leted. These tests cover a broad range of parameters, including both water and steam breaks in the 7 .

drywell, break size, single- and multiple-vent

  • comparisons, effects of initial prAheating and prepurging of the drywell, and effects of initial vent submergence and pool temperature. Data are collected at some 250 active-b

& ( t g s located throughout the CRT facility, with primary emphasis on ,t wetwell response. b DRAFT j The tests conducted to date have evidenced three regimes of containment '.

response: a linear pressurization of the drywell which forces the initial V

water leg from each vent pipe (" air clearing"), followed by an extended period l

of quasi-steady state steam condensation (" condensation oscillation"), leading (

into a highly periodic and dynamic lean suppression phase (" chugging") as the  ;

entrained air concentration in the steam flow depletes. These regimes are consistent with the findings ofOR M L d Mark II experiments, and with (

other BWR containment response experiments not directly addressing the Mark II i design.

The general details of the JAERI CRT response are well documented in publicly available reports. Of particular interest ta U.; ; u .:r.; ca e m d + % -

ue "I is the synchronization of dynamic events throughout the pressure suppression system. The JAERI CRT results consistently indicate strong ,

coupling of pressure response, not only among individual vent pipes, but also among pressure responses in the drywell, vent pipes, and wetwell walls and /

floor. This synchronization, which has been observed in other related full-scale steam condensation experiments at the GKSS Research Center in West l Germany, has a potentially significant impact on the containment loads that ti could be expected in the event of an actual LOCA.

The JAERI CRT program is also concerned with other Mark II containment safety issues, including absolute loads on the wetwell structure, load sensitivity to varioussftemparameters,attenuationofhydrodynamicloads,andtheeffec of fluid-structure interaction on experimental data. This ongoing research contributes significantly not only to the resolution of these issues, but also to clarification of basic pressure suppression phenomenology and to the development and verification of computer models applied to both research e.nd licensing concerns.

DRA?T

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Supplementary Infermation

( l. Affiliation and Mailing Address of Authors Mr. K. Namatame, Dr. Y. Kukita, and Mr. M. Shiba Japan Atomic Energy Research Institute Reactor Safety Lab 1 Tokai-Mura, Naki-gun ,

Ibaraki-Ken 319-11 Japan Dr. E. McCauley and Mr. G. Holman Lawrence Livermore National Laboratory P. O. Box 808, L-140 Livermore, California 94550 U.S.A Please direct correspondence on this summary to Mr. K. Namatame at the address noted above.

2. Related publications:

McCauley, E., et al., "The Effect of Non-Heterogeneous Wetwell Soundaries on Pressure Suppression System Response," submitted to Division B, SMiRT-6 Conference.

( 3. This paper is submitted for consideration in Division F, " Structural Analysis of Thermal Reactor Core and Coolant Circuit Structure."

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