Nuclear Thermal-Hydraulics & Safety LaboratoryUniversity of Nevada, Las Vegas

2026

1 publications
  1. Journal

    Experimental Investigation of Quench Temperature Dependence on Cladding Thickness under Simulated LOCA Conditions

    Fox, N., Dunbar, C., Demo, T., Yeom, H., Corradini, M., Sridharan, K., & Jung, W. H.*

    Nuclear Technology, 1–14

2025

13 publications
  1. Journal

    Impact of Cr-coating on Post-Quench Ductility of Cladding using Ring Compression Testing under Simulated LOCA Condition

    Benda, S., Dunbar, C., Fox, N., Demo, T., Corradini, M., Sridhran, K., Yeom, H. & Jung, W. H.*

    Journal of Nuclear Material, In Preparation

  2. Journal

    Uncertainty analysis of RCCS using MELCOR

    Jung, S., Corradini, M., & Jung, W. H.*

    Annals of Nuclear Energy, submitted

  3. Journal

    Transient behavior of the NuScale 250 MWth Power Module with Cr-coated Zr cladding during a severe accident

    Allaf, M. A., Zaccomer, E., Ejnik, G., Jung, W. H., Corradini, M., & Duarte, J. P.

    Nuclear Technology, 1–14

  4. Journal

    Investigating The Role of Cr-coated Clad During Accident Progression for an SMR Using MELCOR

    Allaf, M. A., Ejnik, G., Zaccomer, E., Jung, W. H., Corradini, M., & Duarte, J. P.

    Nuclear Technology, 1–19

  5. Journal

    Reactor Vessel Cooling System for the GA-EMS Fast Modular Reactor: Experiments and Analysis

    Jung, W. H., Jung, S., Jentz, I., Lindley, B., Anderson, M., Choi, H., Bolin, J. & Corradini, M.

    Nuclear Technology, 1–11

  6. Journal
  7. Journal

    Effect of free falling condition on melt jet breakup length in partially flooded cavity

    Jung, W. H., & Park, H. S.

    Nuclear Engineering and Design, 435, 113923

  8. Conference

    Effect of the initial cladding temperature and subcooling on the quench temperature during single rod reflood experiments

    Jung, W. H., Dunbar, C., Fox, N., Demo, T., Sridharan, K., Corradini, M.

    NURETH-21, Busan, Korea · Young Professional Award

  9. Conference

    Development of the New Jet Breakup Length Correlation Considering the Effect of Vapor Generation Intensity on the Melt Jet Fragmentation

    Jung, W. H. & Park, H. S.

    NURETH-21, Busan, Korea

  10. Conference

    Preliminary Study on Hoop Tensile Properties of Cr-coated SiC-SiC f Composited Cladding

    Shim, D. I., Sridharan, K., Yeom, H., Oswald, S., Deck, C. & Jung, W. H.

    2025 American Nuclear Society Annual Meeting, Chicago, IL

  11. Conference

    Preliminary Study for Cr-coating Effect on Burst Behavior under Simulated LOCA Conditions

    Benda, S., Demo, T., Sridharan, K., Yeom, H. & Jung, W. H.

    2025 American Nuclear Society Annual Meeting, Chicago, IL

  12. Conference

    Cladding Thickness Effect on Quench Temperature under Simulated LOCA Reflood Conditions

    Fox, N., Dunbar, C., Demo, T., Sridharan, K., Corradini, M., Yeom, H. & Jung, W. H.

    2025 American Nuclear Society Annual Meeting, Chicago, IL

  13. Conference

    Thermal Response and Mechanical Integrity of High Temperature Cr-coated Zr Cladding under Multiple Quench Tests

    Jung, W. H., Dunbar, C., Jo, J. Y., Sridharan, K., Yeom, H.

    2025 TMS Annual Meeting

2024

11 publications
  1. Book

    Gas-cooled fast reactor

    Jung, W. H.

    In Nuclear Power Reactor Designs (pp. 245–257). Academic Press.

  2. Journal

    Quenching behavior of high temperature Cr-coated Zr-alloy cladding during bottom reflood condition

    Jung, W. H., Dunbar, C., Fox, N., Demo, T., Corradini, M., Sridharan, K., & Yeom, H.

    International Journal of Heat and Mass Transfer, 232, 125942

  3. Journal

    Fuel performance analysis of Cr-coated Zircaloy-4 cladding during a prototypical LOCA event using BISON

    Dunbar, C., Jung, W., Armstrong, R., Sridharan, K., Corradini, M., & Yeom, H.

    Annals of Nuclear Energy, 200, 110411

  4. Journal

    Source term analysis of FeCrAl accident tolerant fuel using MELCOR

    Baker, U., Choi, Y. J., Rollins, N., Nguyen, K., Jung, W., Whitmeyer, A., ... & Lindley, B.

    Annals of Nuclear Energy, 202, 110482

  5. Journal

    High fidelity core flow measurement experiment for an advanced research reactor using a real scale mockup

    Kim, T., Lee, Y., Hwang, D., Jung, W., Choi, N., Chung, S. S., ... & Jo, H.

    Nuclear Engineering and Technology

  6. Conference

    Reactor Vessel Cooling System for the GA-EMS Fast Modular Reactor: Scaled Experiments and Analysis

    Jung S., Jentz I, Jung W, Lindley B, Anderson M, Corradini M.

    Advances in Thermal Hydraulics (ATH 2024), November 2024

  7. Conference

    Comparison of Pool Quench and Flow Quench Temperature in terms of Temperature Measurement Position

    Jung, W. H., Dunbar, C., Fox, N., Demo, T., Sridharan, K., Corradini, M.

    Advances in Thermal Hydraulics (ATH 2024), November 2024

  8. Conference

    Comparison of Thermal Response and Integrity of Cold Spray Cr-coated and Uncoated ZIRLO Cladding under the Multiple Quenching Tests

    Jung, W. H., Dunbar, C., Fox, N., Demo, T., Armstrong, R., Sridharan, K., Corradini, M. & Yeom, H.

    2024 American Nuclear Society Annual Meeting, Las Vegas, NV

  9. Conference

    Parametric Study of Quenching Behavior of 316L Stainless Steel and ZIRLO Tubes in Simulated LOCA Reflood Conditions

    Fox, N., Jung, W. H., Dunbar, C., Demo, T., Sridharan, K., Corradini, M. & Yeom, H.

    2024 American Nuclear Society Annual Meeting, Las Vegas, NV

  10. Conference

    Sensitivity Analysis of Depressurized Loss of Forced Cooling of Gas-Cooled Fast Modular Reactor using MELCOR

    Jung, S. K., Jung, W. H., Corradini, M., Lindley, B., Bolin, J. & Choi, H.

    2024 American Nuclear Society Annual Meeting, Las Vegas, NV

  11. Conference

    Simulating Radionuclide Retention Experiment in Liquid Sodium Pools using MELCOR code

    Dengler-Jeanblanc, G., Jung, W. H., Corradini, M. & Lindley, B.

    2024 American Nuclear Society Annual Meeting, Las Vegas, NV

2023

6 publications
  1. Journal

    Plant-scale experiments of an air inflow accident under sub-atmospheric pressure by pipe break in an open-pool type research reactor

    Hwang, D., Choi, N., Jung, W., Kim, T., Lee, Y., & Jo, H.

    Nuclear Engineering and Technology, 55(5), 1604–1615

  2. Conference

    Progress in Evaluation of Cr-coated Zr-alloy ATF Cladding under Reactivity-Initiated Accident (RIA) Conditions

    Yeom, H., Sridharan, K., Jung, W. H., Kamerman, D.

    Transactions of the Korean Nuclear Society Autumn Meeting, Gyeongju, Korea

  3. Conference

    Influence of Containment Design Parameters on Analysis of Depressurized Loss of Forced Cooling of Gas-Cooled Fast Modular Reactor using MELCOR Code

    Jung, W. H., Jung, S. K., Dunbar, C. & Corradini, M.

    2023 American Nuclear Society Winter Meeting, Washington, D.C.

  4. Conference

    Effect of Initial Temperature on Quench Behavior of Cr-coated Zr-alloy Cladding

    Dunbar, C., Jung, W. H., Fox, N., Demo, T., Maier, B., Armstrong, R., Sridharan, K., Corradini, M. & Yeom, H.

    2023 American Nuclear Society Winter Meeting, Washington, D.C.

  5. Conference

    Investigation of Cladding Thermal Behavior Under Simulated Reflood Conditions

    Dunbar, C., Jung, W. H., Demo, T., Corradini, M., Sridharan, K., Yeom, H., Armstrong, R., Kamerman, D., Maier, B., Hoffman, A. & Rebak, R.

    NURETH-20, August 23, 2023, pp. 3346–3359

  6. Conference

    Accident Analysis of General Atomics Fast Modular Reactor Plant Model Using MELCOR: DLOFC and PLOFC

    Jung W. H., Dunbar C, Som R, Jung S, Corradini M.

    NURETH-20, August 23, 2023, pp. 3428–3439

2022

4 publications
  1. Conference

    MELCOR Model Development of the General Atomics Fast Modular Reactor: transient accident analysis

    Jung, W. H., Dunbar, C., Wang, J., Corradini, M.

    2022 American Nuclear Society Winter Meeting, Phoenix, AZ, USA

  2. Conference

    MELCOR simulation of a FLiBe natural circulation loop

    Garstka, N., Jung, W. H., Wang, J., Corradini, M.

    2022 American Nuclear Society Winter Meeting, Phoenix, AZ, USA

  3. Conference

    Project overview of thermal-hydraulic and mechanical behavior of near-term ATF design in reflood conditions

    Jung, W. H., Dunbar, C., Corradini, M., Sridharan, K., Kamerman, D., Armstrong, R., Yeom, H.

    2022 American Nuclear Society Winter Meeting, Phoenix, AZ, USA

  4. Conference

    MELCOR Model Development of the General Atomics Fast Gas-Cooled Modular Reactor

    Dunbar, C., Wang, J., Jung, W. H., Corradini, M.

    2022 American Nuclear Society Annual Meeting, Anaheim, CA, USA

2020

3 publications
  1. Journal

    Minimum diameter limit of particle size distribution and its effect on coolability of debris bed

    Jung, W. H., Park, H. S., Oh, J. H., Hwang, B., Lee, M., & Kim, M. H.

    Nuclear Engineering and Design, 363, 110606

  2. Conference

    Effective heating thickness of different method for proper determination of thermal activity of thin heater

    Jung, W. H., Park, H. S. & Kim, M. H.

    Korean Society of Mechanical Engineering Conference

  3. Conference

    Effects of interference grid on melt jet breakup and particle size distribution: MATE-MM-1 & 2 test cases

    Modak, M., Park, H. S., Carlo, E. R., Jung, W. H., Choi, Y. J., Seo, M. R.

    Venue not stated in CV

2019

4 publications
  1. Journal

    Analysis of experimental uncertainties in jet breakup length and jet diameter during molten fuel-coolant interaction

    Jung, W. H., Park, H. S., Moriyama, K., & Kim, M. H.

    Nuclear Engineering and Design, 344, 183–194

  2. Journal

    Numerical validation and investigation for the sedimentation of solid particles in liquid pool using the CFD-DEM coupling algorithm

    Hwang, B., Park, H. S., Jung, W. H., Lee, M., & Kim, M. H.

    Nuclear Engineering and Design, 355, 110364

  3. Conference

    Preliminary study of direct visualization of two-phase flow behavior inside porous media using refractive index matching method

    Oh, J. H., Jung, W. H., Lee, M., Park, H. S., Kim, M. H.

    Transactions of the Korean Nuclear Society Autumn Meeting, Goyang, Korea

  4. Conference

    Modified Rosin-Rammler distribution for debris particle size: Effect of minimum particle size on DHF

    Jung, W. H., Lee, M., Park, H. S., Kim, M. H.

    Transaction of the Korean Nuclear Society Spring Meeting, Jeju, Korea

2018

4 publications
  1. Conference

    Simulation of CCI experiments for the sensitivity analysis with MELCOR 2.2

    Jung, W. H., Hwang, B., Park, H. S., & Moriyama, K.

    Transactions of the Korean Nuclear Society Autumn Meeting, Yeosu, Korea

  2. Conference

    Analysis of particle size distribution by comparing time scales between breakup and solidification in the melt jet breakup phenomenon

    Jung, W. H., Lee, M., Park, H. S., & Moriyama, K.

    NTHAS 11, The 11th Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety, Busan, Korea

  3. Conference

    Importance of the entrance jet shape at the water surface in the Fuel-Coolant Interaction

    Jung, W. H., Park, H. S., Moriyama, K., Kim, M. H.

    Transaction of the Korean Nuclear Society Spring Meeting, Jeju, Korea

  4. Conference

    The Effect of Initial Condition of Melt Jet on the Jet Breakup Phenomenon in the Subcooled Water Pool

    Jung, W. H., Park, H. S., Moriyama, K., & Kim, M. H.

    26th International Conference on Nuclear Engineering, ASME Digital Collection

2017

2 publications
  1. Conference

    Particle Size Distribution by Low Melting Point Alloy FCI Tests and Impact of Distribution Constant on Debris Bed DHF

    Jung, W. H., Lee, M., Moriyama, K., Park, H. S., Kim, M. H.

    Transaction of the Korean Nuclear Society Spring Meeting, Jeju, Korea

  2. Conference

    Experimental investigation of the molten Bi-Sn alloy jet breakup behavior in water using MATE facility

    Jung, W. H., Lee, M., Moriyama, K., Hwang, B., Kim, M. H., & Park, H. S.

    WORTH8, The 8th Korea-China Workshop on Nuclear Reactor Thermo-Hydraulics, Yeosu, Korea

2016

6 publications
  1. Journal

    Analysis of ex-vessel melt jet breakup and coolability. Part 1: Sensitivity on model parameters and accident conditions

    Moriyama, K., Park, H. S., Hwang, B., & Jung, W. H.

    Nuclear Engineering and Design, 302, 107–117

  2. Journal

    Analysis of ex-vessel melt jet breakup and coolability. Part 2: Uncertainty analysis

    Moriyama, K., Park, H. S., Hwang, B., & Jung, W. H.

    Nuclear Engineering and Design, 302, 118–127

  3. Journal

    Experiments on sedimentation of particles in a water pool with gas inflow

    Kim, E., Jung, W. H., Park, J. H., Park, H. S., & Moriyama, K.

    Nuclear Engineering and Technology, 48(2), 457–469

  4. Conference

    Separation of the melt jet breakup length correlation between the strong and weak vapor generation condition

    Jung, W. H., Moriyama, K., & Park, H. S.

    6th Japan-Korea Joint Seminar on Nuclear Thermal Hydraulics and Safety for Students and Young Researchers, Nara, Japan

  5. Conference

    Multiple Boundary Layer Stripping Model by Plateau-Rayleigh Instability for Fuel-Coolant Interactions

    Jung, W. H., Moriyama, K., Park, H. S.

    Transactions of the Korean Nuclear Society Spring Meeting, Jeju, Korea

  6. Conference

    Experimental Revisit of Melt Jet Breakup Length Correlations for Fuel-Coolant Interactions

    Jung, W. H., Moriyama, K., & Park, H. S.

    NUTHOS-11, The 11th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Operation and Safety, Gyeongju, Korea

2015

1 publications
  1. Conference

    Revisit of Melt Jet Breakup Length Correlations for Fuel-Coolant Interactions: Preliminary Experiment Results in the MATE Facility

    Jung, W. H., Moriyama, K., Park, H. S.

    Transactions of the Korean Nuclear Society Autumn Meeting, Gyeongju, Korea