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Analysis of ABWR Containment Pressure-Temperature Loads and Suppression Pool Hydrodynamics Following Loss of Coolant Accidents

[+] Author Affiliations
P. Sawant, M. Khatib-Rahbar

Energy Research, Inc., Rockville, MD

F. Moody

Consultant, Turlock, CA

A. Drozd

U. S. Nuclear Regulatory Commission, Washington, DC

Paper No. PVP2011-57051, pp. 331-340; 10 pages
  • ASME 2011 Pressure Vessels and Piping Conference
  • Volume 5: High-Pressure Technology; Nondestructive Evaluation; Nuclear Engineering
  • Baltimore, Maryland, USA, July 17–21, 2011
  • Conference Sponsors: Pressure Vessels and Piping Division
  • ISBN: 978-0-7918-4455-7
  • Copyright © 2011 by ASME


This paper focuses on the assessment of Advanced Boiling Water Reactor (ABWR) containment pressure-temperature and suppression pool hydrodynamics under design-basis, loss-of-coolant accident (LOCA) conditions. The paper presents a phenomena identification and ranking table (PIRT) applicable to the ABWR containment response behavior, modeling of pressure-temperature loads using the MELCOR computer code, and analysis of suppression pool hydrodynamics parameters based on a mechanistic one-dimensional hydrodynamics model. A MELCOR 1.8.6 model with detailed nodalization of the ABWR containment is used to perform the containment pressure-temperature calculations following a design basis accident. The best estimate and several sensitivity calculations are performed for the ABWR containment using the suppression pool swell model. The sensitivity calculations demonstrate the influence of key model parameters and assumptions on the suppression pool hydrodynamics response. The comparison of containment pressure-temperature and the suppression pool swell analyses results to those reported in the ABWR licensing calculations showed reasonable agreement.

Copyright © 2011 by ASME



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