Published November 1, 2018 | Version v1
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Multiphysical Simulations for the IAEA/ISCP Benchmark Model on the Contact of Pressure Tube and Calandria Tube in the Moderator System of CANDU-6 PHWR

  • 1. Thermal Hydraulic and Severe Accident Research Division, Korea Atomic Energy Research Institute, Republic of Korea
  • 2. Department of Mechanical Engineering, Kunsan National University, Republic of Korea
  • 3. R&D Center, S&H Co. Ltd., Republic of Korea

Description

The LOCA (loss of coolant accident) is a kind of severe accident in the operation of PHWR (pressurized heavy water reactor) as well as other nuclear facilities, and possible cause of LOCA can be counted on the ballooning of pressure tube (PT) contacted to the outer calandria tube (CT) in the moderator system of CANDU-6 reactors. In the paper, we simulated the 150-kW experimental facility proposed by IAEA/ISCP, modeling the transient creeping behavior of pressurized tube heated with thermal radiation between the gaps of two concentric pipes. The outer boundary is simplified with a switched model that depends on the local temperature. With a multiphysical model supported by a commercial code, COMSOL multiphysics, the unsteady phenomena are simulated with models concerning various kinds of mechanics such as thermodynamics, nonlinear structural dynamics, and two-phase boiling heat transfer models.

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Additional details

Identifiers

Publishing Information

Journal Title
Science and Technology of Nuclear Installations
Journal Volume
2018
Journal Page Range
1-8
ISSN
1687-6075

Optional Information

Copyright
© Author(s)
Contract/Grant/Project number
20174010201350, NRF-2017M1A3A3A03015448
Notes
Record automatically processed
Funding organization
Human Resources Development Program, Space Core Technology Development Program