한국원자력학회:학술대회논문집 (Proceedings of the Korean Nuclear Society Conference)

한국원자력학회 (Korean Nuclear Society)
권호 표지

A Thermal hydraulic Investigation on ADSR Liquid Lead Target

  • Kim, Ju Y. (Seoul National University) ;
  • Byung G. Huh (Seoul National University) ;
  • Chang H, Chung (Seoul National University) ;
  • Tae Y. song (Korea Atomic Energy Research Institute) ;
  • Park, Won S. (Korea Atomic Energy Research Institute)
  • 발행 : 1998.05.01
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초록

Computational fluid dynamics(CFD) code FLUENT[11 was used to simulate the thermal hydraulic processes occuring in conceptual design of the accelerator-driven subcritical reactor(ADSR) liquid lead target. The purpose of the analysis is to investigate the thermal hydraulic characteristics of liquid lead as ADSR target material with various target geometries and injection locations of proton beam. In the calculation analysis, the local temperature of the liquid lead target rises to the boiling temperature very rapidly When the proton beam is injected from the bottom of the target system, the duration time to reach the boiling temperature is longer and the temperature distribution is flatter than other cases.

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