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A variety of Generation III/III+ water-cooled reactor designs featuring enhanced safety and improved economics are being proposed by nuclear power industries around the world in efforts to solve the future energy supply shortfall. Thermal-hydraulics is recognized as a key scientific subject in the development of innovative reactor systems. Applications are being advanced with the introduction of new technologies such as nanotechnology. Nanofluids are potential heat transfer fluids with enhanced thermophysical properties and heat transfer performance can be applied in many devices for better performances. Recent researches have indicated that substitution of conventional coolants by nanofluids appears promising. Specific application of nanofluids in engine cooling, solar water heating, cooling of electronics, cooling of transformer oil, improving diesel generator efficiency, cooling of heat exchanging devices, improving heat transfer efficiency of chillers, domestic refrigerator-freezers, cooling in machining, in nuclear reactor and defense and space have been applied.

The development of viable nanofluids for use in water-cooled nuclear systems could result in a significant improvement of their economic performance and/or safety margins. Especially, it was determined that the system has a reasonably low failure probability, and that, once injected, the nanofluid would be delivered effectively to the reactor vessel surface within seconds. It was also shown analytically that the increase in decay power removal through the vessel using a nanofluid is about 40%, which could be exploited to provide higher in-vessel retention (IVR) safety margin or, for a given margin, to enable IVR at higher core power.

 

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Fig. 3-1 Growth of publications by the nanofluids community

 

 

 

 

 

 

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Fig. 3-2 Comparison of the thermal conductivity of common liquids, polymers, and solids

 

 

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Fig. 3-3 Required heat removal capacity

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January 10th, 2019

2019 Journals

Journals Seok Bin Seo, In Cheol Bang*, Acoustic analysis on the dynamic motion of vapor-liquid interface for the identification of […]

December 21st, 2018

Books/Chapters

Books 예제로 배우는 원자로 시스템 시뮬레이션, 방인철, 최기용, 김형태, 김수형, 서경원, 허선 공저, 홍릉과학출판사 에너지 과학: 원리, 기술, 영향, 김철주, […]

December 21st, 2018

Patent

등록 (Registered) 그라핀 / 그라핀-산화물 분산 냉각재의 이용방법 및 이를 이용한 원자로 노심용융물 냉각 시스템, 등록번호: 10-1106456, 대한민국, 2012.01.10, 출원인: […]

April 13th, 2018

2018 Journals

Journals Seok Bin Seo, Yukyung Shin, In Cheol Bang*, Numerical Analysis on Spatial Universality of Similarity Technique inside Molten Salt […]

January 27th, 2018

2017 Conferences

Conference Yeong Shin Jeong, In Cheol Bang, Experimental study on performance of U-pattern wire wrap spacer of fast reactor fuel […]

January 21st, 2017

2016 Conferences

Yukyung Shin, Seok Bin Seo, In Guk Kim, In Cheol Bang, Sensitivity Study of Thermophysical Properties for LiF-BeF2 and Simulant […]

December 16th, 2016

2017 Journals

Journals K. M. Kim, I. C. Bang, “Heat transfer characteristics and operation limit of pressurized hybrid heat pipe for small […]

February 5th, 2016

Curriculum

Undergraudates [NUE300] Nuclear System Engineering and Experiment [NUE400] Nuclear Engineering Design & Lab. Graduates [NUE508] Nuclear System Engineering and Design […]

January 27th, 2016

2015 Conferences

Conference International Conference KM Kim, YS Jeong, IG Kim, IC Bang*, “Development of Passive In-Core Cooling System (PINCs) Based on […]

November 27th, 2015

2016 Journals

Journals I. G. Kim, K. M. Kim, Y. S. Jeong, I. C. Bang*, “Performance of annular flow path heat pipe […]