Article ID | Journal | Published Year | Pages | File Type |
---|---|---|---|---|
8067714 | Annals of Nuclear Energy | 2016 | 16 Pages |
Abstract
The MARS-LMR code has been developed to analyze transients in a pool-type sodium-cooled fast reactor (SFR) which has been designed by the Korea Atomic Energy Research Institute (KAERI). Currently, KAERI has developed a prototype Gen-IV SFR (PGSFR) with metallic fuel. The MARS-LMR code is based on the MARS code, and supplements various liquid metal related features including sodium properties, sodium heat transfer and pressure drop models. In order to validate the newly developed MARS-LMR, KAERI has joined the International Atomic Energy Agency (IAEA) coordinated research project (CRP) on the “Benchmark Analysis of an EBR-II shutdown heat removal test” (Briggs et al., 2013, 2015). Argonne National Laboratory (ANL) has operated the EBR-II technically supported and is participating in this program (Sumner and Wei, 2012). In addition, various institutes and countries have joined the IAEA-CRP. The EBR-II SHRT-17 is a kind of loss of flow test, and thus sodium natural circulation is a major phenomenon. The benchmark analysis is conducted using MARS-LMR with the original input data provided by ANL. Qualitatively, MARS-LMR predicted well the natural circulation flow in the core. In addition, sensitivity tests were carried out for various influential parameters to get a better prediction. This study can give validation data for MARS-LMR and a better understanding of EBR-II SHRT-17.
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Authors
Chiwoong Choi, Kwiseok Ha,