List

9_1

Ga-cooled Passive Decay Heat Removal System

  • Preliminary Concept of Advanced passive decay heat removal system (PDHRS) using gallium for SFR

The attractive properties ensure that gallium can play an important role in nuclear safety as an alternative coolant of the decay heat removal system of the SFR. In particular, there is an emphasis to passive safety system in nuclear reactor design so that reactors can be made more tolerant of failing, and have less dependence on engineers. The passive safety natural convection systems for decay heat removal have several benefits such as simplicity, reduction of the cost and usage problems of pumps. They are contributed to set the power plant in a safe and stable condition. Therefore, this study aims to experimentally investigate the natural convection capability of gallium as a feasibility study for the development of gallium-based passive safety features.

 

  • Thermal-hydraulic analysis of a single-phase natural convection loop for liquid metal with MARS-LMR and computational fluid dynamics

This work discusses the results by using MARS-LMR code having Ga property table and computational fluid dynamics for the comparison of the heat transfer characteristics gained in experiments carried out in a single-phase natural convection loop. The loop consists of a vertical heating and cooling section and working fluid is liquid gallium. The experiment shows the natural convection capability of gallium by determining a flowrate formed according to a level of the heat input. By using the dimensionless numbers, the correlations in the tube at natural convection of gallium also are represented. This study can contribute to an advanced design of passive decay heat removal system with adopting a safer coolant to secure the safety more tightly of the current typical designs of sodium-cooled reactor.

9_2

Test facility

9_3

Nodalization and computational fluid dynamics analysis of test facility

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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 […]