1
|
He M, Ali A, Chen M. Experimental investigations of Critical Heat Flux re-occurrence on post-CHF surfaces. PROGRESS IN NUCLEAR ENERGY 2022. [DOI: 10.1016/j.pnucene.2022.104211] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/18/2022]
|
2
|
Kam DH, Jeong YH, Choi SM, Yun JI. Magnetic withdrawal of particles for multiple purposes in nuclear power plants. NUCLEAR ENGINEERING AND TECHNOLOGY 2021. [DOI: 10.1016/j.net.2021.06.037] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/21/2022]
|
3
|
He M, Wang J, Chen M. Recent progresses on thermal–hydraulics evaluations of accident tolerant fuel cladding materials. ANN NUCL ENERGY 2021. [DOI: 10.1016/j.anucene.2021.108391] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.7] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/21/2022]
|
4
|
Yeom H, Gutierrez E, Jo H, Zhou Y, Mondry K, Sridharan K, Corradini M. Pool boiling critical heat flux studies of accident tolerant fuel cladding materials. NUCLEAR ENGINEERING AND DESIGN 2020. [DOI: 10.1016/j.nucengdes.2020.110919] [Citation(s) in RCA: 6] [Impact Index Per Article: 1.5] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/23/2022]
|
5
|
Experimental Investigation of Critical Heat Flux on Different Surfaces at Low Pressure and Low Flow. ENERGIES 2020. [DOI: 10.3390/en13195205] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Abstract] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/16/2022]
Abstract
Steady state flow boiling experiments were carried out on several heated tubes with outer diameter 9.14 mm at outlet pressures 120, 200 and 300 kPa, inlet temperatures 64, 78 and 91 °C and approximately 400, 500, 600 and 800 kg/(m2·s) mass flux entering the vertically aligned test annulus until critical heat flux (CHF) was reached. The tubes were made of Inconel 625 with a length of 400 mm. The Inconel tubes were tested in three different modifications as smooth, abraded with 150 grit sandpaper and bead blasted. Multiple experiments were repeated on the same specimen to investigate the effect of surface characteristic changes (i.e., wettability, roughness and oxide layer morphology) on the occurrence of CHF. Despite the changes in initial wettability, the CHF dependency was not clearly observed, however, the changes in roughness led to an increase in CHF. The total number of 115 experimental runs were collected and the results were also compared with other literature experimental data.
Collapse
|
6
|
Ali A, Kim HG, Hattar K, Briggs S, Jun Park D, Hwan Park J, Lee Y. Ion irradiation effects on Cr-coated zircaloy-4 surface wettability and pool boiling critical heat flux. NUCLEAR ENGINEERING AND DESIGN 2020. [DOI: 10.1016/j.nucengdes.2020.110581] [Citation(s) in RCA: 4] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/24/2022]
|
7
|
Kam DH, Choi YJ, Jeong YH. Boric acid and boiling time effects on critical heat flux for corrosive and non-corrosive materials. ANN NUCL ENERGY 2020. [DOI: 10.1016/j.anucene.2019.106999] [Citation(s) in RCA: 4] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/26/2022]
|
8
|
Evaluation of critical heat flux of ATF candidate coating materials in pool boiling. NUCLEAR ENGINEERING AND DESIGN 2019. [DOI: 10.1016/j.nucengdes.2019.110166] [Citation(s) in RCA: 16] [Impact Index Per Article: 3.2] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/22/2022]
|
9
|
Kang JY, Kim TK, Lee GC, Jo H, Kim MH, Park HS. Impact of system parameters on quenching heat transfer in the candidate materials for accident tolerant fuel-cladding in LWRs. ANN NUCL ENERGY 2019. [DOI: 10.1016/j.anucene.2019.01.015] [Citation(s) in RCA: 15] [Impact Index Per Article: 3.0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/30/2022]
|
10
|
Cheol Lee G, Noh H, Yeom H, Jo H, Kyun Kim T, Kim M, Sridharan K, Sun Park H. Zirconium-silicide coating on zircaloy-4 substrate for accident tolerance: Effects on oxidation resistance and boiling. ANN NUCL ENERGY 2019. [DOI: 10.1016/j.anucene.2018.11.019] [Citation(s) in RCA: 16] [Impact Index Per Article: 3.2] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/27/2022]
|
11
|
Kang JY, Kim TK, Lee GC, Kim MH, Park HS. Quenching of candidate materials for accident tolerant fuel-cladding in LWRs. ANN NUCL ENERGY 2018. [DOI: 10.1016/j.anucene.2017.11.007] [Citation(s) in RCA: 21] [Impact Index Per Article: 3.5] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/16/2022]
|