본문 바로가기
KERD
논문KCI 등재

Can a nanofluid enhance the critical heat flux if the recirculating coolant contains debris?

0

조회

0

다운로드

0

인용

0

참고문헌

키워드

주제분류원자력공학

초록

In-vessel corium retention (IVR) during external reactor vessel cooling (ERVC) is a key severe accidentmanagement strategy adopted in advanced nuclear power plants. The injection of nanofluids has beenregarded as a means of enhancing CHF when using the IVR-ERVC strategy to safeguard high-powernuclear reactors. However, a critical practical concern is that various types of debris flowing from thecontaminant sump during operation of an ERVC system might degrade CHF enhancement by nanofluids. Our objective here was to experimentally assess the viability of nanofluid use to enhance CHF in practicalERVC contexts (e.g., when fluids contain various types of debris). The types and characteristics of debrisexpected during IVR-ERVC were examined. We performed pool boiling CHF experiments using nanofluids containing these types of debris. Notably, we found that debris did not cause any degradation ofthe CHF enhancement characteristics of nanofluids. The nanoparticles are approximately 1000-foldsmaller than the debris particles; the number of nanoparticles in the same volume fraction is 1billion-fold greater. Nanofluids increase CHF via porous deposition of nanosized particles on the boilingsurface; this is not hindered by extremely large debris particles

Abstract

In-vessel corium retention (IVR) during external reactor vessel cooling (ERVC) is a key severe accidentmanagement strategy adopted in advanced nuclear power plants. The injection of nanofluids has beenregarded as a means of enhancing CHF when using the IVR-ERVC strategy to safeguard high-powernuclear reactors. However, a critical practical concern is that various types of debris flowing from thecontaminant sump during operation of an ERVC system might degrade CHF enhancement by nanofluids. Our objective here was to experimentally assess the viability of nanofluid use to enhance CHF in practicalERVC contexts (e.g., when fluids contain various types of debris). The types and characteristics of debrisexpected during IVR-ERVC were examined. We performed pool boiling CHF experiments using nanofluids containing these types of debris. Notably, we found that debris did not cause any degradation ofthe CHF enhancement characteristics of nanofluids. The nanoparticles are approximately 1000-foldsmaller than the debris particles; the number of nanoparticles in the same volume fraction is 1billion-fold greater. Nanofluids increase CHF via porous deposition of nanosized particles on the boilingsurface; this is not hindered by extremely large debris particles

참고문헌 (13)

  1. J. W. Park, "Assessment of In-Vessel Core Debris Cool-Ability for the APR1400 Design, Final Peer-Review Version" (2001), Korea Hydro & Nuclear Power Co
  2. Invessel Coolability and Retention of a Core Melt, "T. G. Theofanous", ~, pp.DOE (1996), ID-10460
  3. S. M. You, "Effect of nanoparticles on critical heat flux of water in pool boiling heat transfer", Appl. Phys. Lett, 83, pp.3374~ (2003)
  4. P. Vassallo, "Pool boiling heat transfer experiments in silica-water nano-fluids", Int. J. Heat Mass Tran, 47, pp.407~ (2004)
  5. I. C. Bang, "Boiling heat transfer performance and phenomena of Al2O3-water nano-fluids from a plain surface in a pool", Int. J. Heat Mass Tran, 48, pp.2407~ (2005)
  6. 김형대, "EXPERIMENTAL STUDY ON CHF CHARACTERISTICS OFWATER-TIO2 NANO-FLUIDS", Nuclear Engineering and Technology, 38(1), pp.61~68 (2006), 한국원자력학회
  7. Effectiveness of External Reactor Vessel Cooling (ERVC)Strategy for APR1400 and Issues of Phenomenological Uncertainties, "S. J. Oh", Nuclear Environmental Technology Institute, Korea Hydro & Nuclear Power Co., Ltd, ~ (2005)
  8. I. C. Bang, "An axiomatic design approach of nanofluid-engineered nuclear safety features for generation IIIþ reactors", Nuclear Engineering and Technology, 41(9), pp.1157~ (2008)
  9. Knowledge Base for the Effect of Debris on Pressurized Water Reactor Core Cooling Sump Performance, "Los Alamos National Laboratory", ~, pp.NUREG (2003), CR-6808
  10. "Personal Communication with FNC Technology Co., Ltd", ~
  11. J. P. Holman, "Experimental Methods for Engineers" (2001), McGraw-Hill
  12. W. M. Rohsenow, "A method of correlating heat transfer data for surface boiling liquids", Trans. ASME, 74(6), pp.969~ (1952)
  13. N. Zuber, "Hydrodynamic aspects of boiling heat transfer", AEC Rep. AECU 4439, ~ (1959)

관련 논문AI추천

이 간행물의 다른 논문 (22건)