List

5_1

 

Wall temperature variation during water reflood

 

In a nuclear reactor system, the emergency core cooling system (ECCS) provides backup to the cooling system for prevent the melt of core and fuel assembly especially at the Loss of coolant accident (LOCA). In this state as like LOCA, firstly blowdwon occurred in the reactor core after that control rod is inject to the core for shutdown for core. But decay heat emitted in fuel assembly it is 6% of operating power. It can be cooled by injected coolant by the reflooding. If it doesn’t rapidly removed by coolant, nuclear fuel can be melted by high temperature and exposed by fission gas.

Injected water interacts with heated wall. In this situation, reflood shows phase change. We investigate reflood state with phenomenon. Furthermore, we research the enhanced coolant by using nanofluid. Enhanced coolant can be adopted for coolant for ECCS. It can useful to increase of operation time in the accident.

 

5_2

 

Facility of reflood experiment

 

 

 

5_3

 

Cladding surface temperature during LOCA

 

 

5_4

 

Wall temperature variation during water reflood

 

  Posts

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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 […]