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Employment (2)

University of Tsukuba: Tsukuba, Ibaraki, JP

2022-02-01 to present | Assistant Professor (Faculty of Engineering, Information and Systems)
Employment
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University of Tsukuba

The University of Tokyo: Tokyo, JP

2019-10-01 to 2022-01-31 | Postdoc
Employment
Source: Self-asserted source
kai wang

Works (29)

Debris bed coolability in hypothetical core disruptive accidents: Theory, experiment, and numerical simulation review

Progress in Nuclear Energy
2025-06 | Journal article
Contributors: Yonglong Li; Shaojie Tan; Yubin Lin; Kai Wang; Songbai Cheng
Source: check_circle
Crossref

Development of a semiempirical model for the aerosol scrubbing in a sodium pool

Progress in Nuclear Energy
2025-06 | Journal article
Contributors: Gen Jiang; Mou Wang; Jingyu Guo; Kai Wang; Songbai Cheng
Source: check_circle
Crossref

Effect of gap size and inclination angle on Critical Heat Flux (CHF) of pool boiling based on bubble behavior observations

Progress in Nuclear Energy
2025-06 | Journal article
Contributors: Yanxu Huang; Ken Chen; Junfeng Li; Zihao Wang; Kai Wang; Shixian Wang
Source: check_circle
Crossref

Re-examining the input-parameters and AI strategies for Critical Heat Flux prediction

Energy
2025-03 | Journal article
Contributors: Kai Wang; Da Wang; Xiaoxing Liu; Songbai Cheng; Shixian Wang; Wen Zhou; Shuichiro Miwa; Koji Okamoto
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Crossref

Review of the research on the scrubbing of fission products in liquid metal pool

Nuclear Engineering and Design
2024-05 | Journal article
Contributors: Gen Jiang; Mou Wang; Kai Wang; Songbai Cheng
Source: check_circle
Crossref

Numerical simulation of aerosol generation by cutting fuel debris and aerosol removal by spray droplets during Fukushima decommissioning

Progress in Nuclear Energy
2023-06 | Journal article
Contributors: Hui Liang; Nejdet Erkan; Kai Wang; Avadhesh Kumar Sharma; Shunichi Suzuki
Source: check_circle
Crossref

Effects of surface alteration on CHF related to IVR accident scenarios: A review

Progress in Nuclear Energy
2023-05 | Journal article
Contributors: Bowen Qiu; Xiaoxing Liu; Kai Wang; Songbai Cheng; Zhenhan Hong; Koji Okamoto
Source: check_circle
Crossref

Experimental investigation on the characteristics of bubble growth and slide on a downward-facing heater surface in flow boiling

International Journal of Thermal Sciences
2023-02 | Journal article
Contributors: Kai Wang; Zhenhan Hong; Hui Liang; Inoue Junya; Songbai Cheng; Koji Okamoto
Source: check_circle
Crossref

Numerical Simulation and Validation of Debris Bed Self-Leveling Behavior with Mixed-Density Particles Using CFD-DEM Coupling Algorithm

Nuclear Technology
2022-05-04 | Journal article
Contributors: Chun-Yen Li; Kai Wang; Marco Pellegrini; Nejdet Erkan; Koji Okamoto
Source: check_circle
Crossref
grade
Preferred source (of 2)‎

A preliminary study on material effects of critical heat flux for downward-facing flow boiling

Nuclear Engineering and Technology
2021 | Journal article
EID:

2-s2.0-85105102696

Part of ISSN: 2234358X 17385733
Contributors: Wang, K.; Li, C.-Y.; Uesugi, K.; Erkan, N.; Okamoto, K.
Source: Self-asserted source
kai wang via Scopus - Elsevier

CHF enhancement for a finned surface in flow boiling with explanations based on vapor observations

Progress in Nuclear Energy
2021-08 | Journal article
Contributors: Kai Wang; Hui Liang; Chun-Yen Li; Nejdet Erkan; Koji Okamoto
Source: check_circle
Crossref
grade
Preferred source (of 2)‎

Extended development of a bubble percolation method to predict boiling crisis of flow boiling

International Journal of Heat and Mass Transfer
2021-02 | Journal article
Contributors: Kai Wang; Chun-Yen Li; Marco Pellegrini; Nejdet Erkan; Koji Okamoto
Source: check_circle
Crossref
grade
Preferred source (of 2)‎

A study on the effect of oxidation on critical heat flux in flow boiling with downward-faced carbon steel

International Journal of Heat and Mass Transfer
2020 | Journal article
EID:

2-s2.0-85074263079

Part of ISSN: 00179310
Contributors: Wang, K.; Erkan, N.; Okamoto, K.
Source: Self-asserted source
kai wang via Scopus - Elsevier

Effects of a porous honeycomb structure on critical heat flux in downward-facing saturated pool boiling

Applied Thermal Engineering
2020 | Journal article
EID:

2-s2.0-85078978836

Part of ISSN: 13594311
Contributors: Wang, K.; Gong, H.; Wang, L.; Erkan, N.; Okamoto, K.
Source: Self-asserted source
kai wang via Scopus - Elsevier

Irradiation effects of CHF on bare and porous honeycomb surface in downward-face saturated pool boiling

Progress in Nuclear Energy
2020 | Journal article
EID:

2-s2.0-85088151533

Part of ISSN: 01491970
Contributors: Wang, K.; Gong, H.; Wang, L.; Erkan, N.; Okamoto, K.
Source: Self-asserted source
kai wang via Scopus - Elsevier

Metal material surface wettability increase induced by electron beam irradiation

Applied Surface Science
2020 | Journal article
EID:

2-s2.0-85078702903

Part of ISSN: 01694332
Contributors: Wang, L.; Wang, K.; Erkan, N.; Yuan, Y.; Chen, J.; Nie, B.; Li, F.; Okamoto, K.
Source: Self-asserted source
kai wang via Scopus - Elsevier

Oxidation effect of copper on the downward-facing flow boiling CHF under atmospheric condition

International Journal of Heat and Mass Transfer
2020 | Journal article
EID:

2-s2.0-85084656567

Part of ISSN: 00179310
Contributors: Wang, K.; Erkan, N.; Okamoto, K.
Source: Self-asserted source
kai wang via Scopus - Elsevier

A new model for predicting the critical heat flux based on nucleation site density in downward-face boiling

Journal of Nuclear Science and Technology
2019 | Journal article
EID:

2-s2.0-85075113237

Part of ISSN: 00223131
Contributors: Wang, K.; Erkan, N.; Okamoto, K.
Source: Self-asserted source
kai wang via Scopus - Elsevier

CFD prediction of ultra-high critical heat flux for subcooled water flow boiling in a vertical tube

18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019
2019 | Conference paper
EID:

2-s2.0-85073726531

Contributors: Wang, K.; Erkan, N.; Okamoto, K.
Source: Self-asserted source
kai wang via Scopus - Elsevier

Effect of finned structure on critical heat flux (CHF) in downward-face pool boiling

International Conference on Nuclear Engineering, Proceedings, ICONE
2019 | Conference paper
EID:

2-s2.0-85071370967

Contributors: Wang, K.; Erkan, N.; Cai, R.; Okamoto, K.
Source: Self-asserted source
kai wang via Scopus - Elsevier

Effects of carbon steel surface oxidation on critical heat flux in downward-face pool boiling

International Journal of Heat and Mass Transfer
2019 | Journal article
EID:

2-s2.0-85062443568

Part of ISSN: 00179310
Contributors: Wang, K.; Erkan, N.; Gong, H.; Okamoto, K.
Source: Self-asserted source
kai wang via Scopus - Elsevier

Effects of heaving condition on characteristics of system under forced circulation and natural circulation

International Conference on Nuclear Engineering, Proceedings, ICONE
2019 | Conference paper
EID:

2-s2.0-85071393831

Contributors: Cai, R.; Mi, Z.; Yue, N.; Fang, H.; Qiu, S.; Wang, K.; Qiu, Z.
Source: Self-asserted source
kai wang via Scopus - Elsevier

Experiment and numerical simulation of a single bubble formation under a downward face of different contact angels

18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019
2019 | Conference paper
EID:

2-s2.0-85073744779

Contributors: Wang, K.; Erkan, N.; Okamoto, K.
Source: Self-asserted source
kai wang via Scopus - Elsevier

Comparison of pool boiling CHF of a polished copper block and carbon steel block on a declined slope

Journal of Nuclear Science and Technology
2018 | Journal article
EID:

2-s2.0-85047140280

Part of ISSN: 00223131
Contributors: Wang, K.; Erkan, N.; Gong, H.; Wang, L.; Okamoto, K.
Source: Self-asserted source
kai wang via Scopus - Elsevier

Preliminary research on the oxidation effect of the carbon steel plate of downward facing pool boiling by two-dimensional image

International Conference on Nuclear Engineering, Proceedings, ICONE
2018 | Conference paper
EID:

2-s2.0-85056156906

Contributors: Wang, K.; Erkan, N.; Okamoto, K.
Source: Self-asserted source
kai wang via Scopus - Elsevier

Control system design for NuScale

International Conference on Nuclear Engineering, Proceedings, ICONE
2017 | Conference paper
EID:

2-s2.0-85032568661

Contributors: Wang, K.; Sun, P.
Source: Self-asserted source
kai wang via Scopus - Elsevier

Development and verification of thermal hydraulic subchannel analysis code for motion conditions

International Conference on Nuclear Engineering, Proceedings, ICONE
2016 | Conference paper
EID:

2-s2.0-84995584917

Contributors: Cai, R.; Huang, S.; Wang, K.; Tian, W.; Qiu, S.; Su, G.
Source: Self-asserted source
kai wang via Scopus - Elsevier

CFD simulations of thermal mixing at ECC safety injection for single phase and air-water bubbly phase flow

International Conference on Nuclear Engineering, Proceedings, ICONE
2015 | Conference paper
EID:

2-s2.0-84959056228

Contributors: Wang, K.; Ren, W.; Qiu, S.; Tian, W.; Su, G.; Wu, J.
Source: Self-asserted source
kai wang via Scopus - Elsevier

Simulations of ECC safety injection for single phase and stratified phase flow

International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015
2015 | Conference paper
EID:

2-s2.0-84983111572

Contributors: Wang, K.; Cai, R.; Ren, W.; Qiu, S.; Tian, W.; Su, G.H.; Chen, R.
Source: Self-asserted source
kai wang via Scopus - Elsevier