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Home / Publications / Journals / Nuclear Technology / Volume 156 / Number 3

Improvement of the Subchannel Flow Mixing Model of the MARS Code

Jae Jun Jeong, Dae Hyun Hwang, Bub Dong Chung

Nuclear Technology / Volume 156 / Number 3 / December 2006 / Pages 360-368

Technical Note / Thermal Hydraulics /

MARS is a best-estimate system analysis code that is based on the RELAP5/MOD3 and COBRA-TF codes. The COBRA-TF code was adapted as a three-dimensional thermal-hydraulic module in MARS. It uses a two-fluid, three-field model for two-phase flows and has a subchannel flow mixing model. The subchannel flow mixing model of the MARS three-dimensional module was assessed by using the ISPRA 16-rod bundle test and the GE 9-rod bundle test data. These tests represent typical pressurized water reactor and boiling water reactor core thermal-hydraulic conditions, respectively. Two interconnected subchannel tests that were performed under atmospheric pressure conditions were also used for the assessment. From the results of the assessments, a simple modification of the subchannel flow mixing model was suggested to take into account the effects of the system pressure on the void drift phenomena.

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