Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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The DISNY facility for sub-cooled flow boiling performance analysis of CRUD deposited zirconium alloy cladding under pressurized water reactor condition: Design, construction, and operation

  • Ji Yong Kim (Department of Nuclear Engineering, Ulsan National Institute of Science and Technology (UNIST)) ;
  • Yunju Lee (Department of Nuclear Engineering, Ulsan National Institute of Science and Technology (UNIST)) ;
  • Ji Hyun Kim (Department of Nuclear Engineering, Ulsan National Institute of Science and Technology (UNIST)) ;
  • In Cheol Bang (Department of Nuclear Engineering, Ulsan National Institute of Science and Technology (UNIST))
  • Received : 2023.01.06
  • Accepted : 2023.06.02
  • Published : 2023.09.25
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Abstract

The CRUD on the fuel cladding under the pressurized water reactor (PWR) operating condition causes several issues. The CRUD can act as thermal resistance and increases the local cladding temperature which accelerate the corrosion process. The hideout of boron inside the CRUD results in axial offset anomaly and reduces the plant's shutdown margin. Recently, there are efforts to revise the acceptance criteria of emergency core cooling systems (ECCS), and additionally require the modeling of the thermal resistance effect of the CRUD during the performance analysis. There is an urgent need for the evaluation of the effect of the CRUD deposition on the cladding heat transfer under PWR operating conditions, but the experimental database is very limited. The experimental facility called DISNY was designed and constructed to analyze the CRUD-related multi-physical phenomena, and the performance analysis of the constructed DISNY facility was conducted. The thermal-hydraulic and water chemistry conditions to simulate the CRUD growth under PWR operating conditions were established. The design characteristics and feasibility of the DISNY facility were validated by the MARS-KS code analysis and separate performance tests. In the current study, detailed design features, design validation results, and future utilization plans of the proposed DISNY facility are presented.

Keywords

Acknowledgement

This work was supported by the Nuclear Safety Research Program through the Korea Foundation Of Nuclear Safety (KoFONS) using the financial resource granted by the Nuclear Safety and Security Commission (NSSC) of the Republic of Korea. (No. 2106022).

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