Search Results - "Tiep, Nguyen Huu"

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  1. 1

    A three-dimensional CFD simulation of corium jet breakup in intensive vapor generation condition by Eom, Jeong-Hyun, Choi, Ji-Won, Tak, Gi-Young, Ra, In-Sik, Nguyen, Huu Tiep, Jeong, Hae-Yong

    Published in Nuclear engineering and technology (01-12-2024)
    “…The complexity of ex-vessel phenomena during a severe accident limits the most previous CFD applications only to hydrodynamic aspects. The present study…”
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    Journal Article
  2. 2

    Evaluation of jet breakup length with a CFD code under steam generation condition in a pre-flooded cavity by Eom, Jeong-Hyeon, Tak, Gi-Young, Ra, In-Sik, Nguyen, Huu Tiep, Jeong, Hae-Yong

    Published in Nuclear engineering and technology (01-07-2023)
    “…When the reactor vessel is penetrated in a severe accident of light water reactor, the molten fuel-coolant interaction including the jet breakup occurs and the…”
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  3. 3

    A newly proposed data assimilation framework to enhance predictions for reflood tests by Huu Tiep, Nguyen, Kim, Kyung-Doo, Heo, Jaeseok, Choi, Chi-Woong, Jeong, Hae-Yong

    Published in Nuclear engineering and design (15-04-2022)
    “…[Display omitted] •The higher acceptance rates and faster computational performance.•A new accuracy evaluation and Monte Carlo sampling approach are…”
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  4. 4

    Novel gain-tuning for sliding mode control of second-order mechanical systems: theory and experiments by Xuan-Mung, Nguyen, Nguyen, Ngoc Phi, Pham, Dinh Ba, Dao, Nhu-Ngoc, Nguyen, Huu Tiep, Ha Le Nhu Ngoc, Thanh, Vu, Mai The, Hong, Sung Kyung

    Published in Scientific reports (29-06-2023)
    “…The sliding mode control is well-known as a useful control technique that can be applied in several real-world applications. However, a straightforward and…”
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  5. 5

    Sensitivity and uncertainty analysis of the first core of the DNRR using MCNP6 and new nuclear data libraries by Chu, Thoi-Nam, Phan, Giang T.T., Tran, Le Quang Linh, Bui, Thi Hong, Do, Quang Binh, Dau, Duc-Tu, Nguyen, Kien-Cuong, Nguyen, Nhi-Dien, Nguyen, Huu-Tiep, Hoang, Van-Khanh, Vu, Thanh Mai, Tran, Hoai-Nam

    Published in Nuclear engineering and design (01-04-2024)
    “…This paper presents the sensitivity and uncertainty analysis for the Dalat Nuclear Research Reactor (DNRR) using MCNP6.2 and several data libraries such as…”
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  6. 6

    Core design optimization of a 200 MWt pressurized water SMR using evolutionary simulated annealing by Hoang, Van-Khanh, Phan, Giang T.T., Tran, Viet-Phu, Chu, Thoi-Nam, Nguyen, Huu-Tiep, Phan, Haidang, Bui, Van-Loat, Tran, Hoai-Nam

    Published in Nuclear engineering and design (01-03-2024)
    “…The paper presents the design optimization of a pressurized small modular reactor (SMR) core using evolutionary simulated annealing (ESA). The core was…”
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  7. 7

    Enhancement of Reflood Test Prediction by Integrating Machine Learning and Data Assimilation Technique by Tiep, Nguyen Huu, Kim, Jong-Sung, Jeong, Hae-Yong, Kim, Kyung-Doo, Xuan-Mung, Nguyen, Tran, Hoai-Nam, Anh, Nguyen Ngoc

    Published in International journal of energy research (28-05-2024)
    “…Data assimilation (DA) was revealed as a highly efficient approach to enhance the prediction’s accuracy, demonstrating the reliability of the simulation…”
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  8. 8

    Investigation of the VVER-1000 reactor pressure vessel neutron fluence and displacement per atom using MCNP6 by Tiep, Nguyen Huu, Hoang, Sy Minh Tuan, Hartanto, Donny, Kim, Kyung Doo, Kim, Jong Kyung, Tuan, Nguyen Minh, Ha, Pham Nhu Viet

    “…Ensuring the integrity of the reactor pressure vessel (RPV) during the operating life of nuclear reactors is of paramount importance, and hence the harmful…”
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  9. 9

    Output Feedback Control for Spacecraft Attitude System with Practical Predefined-Time Stability Based on Anti-Windup Compensator by Xuan-Mung, Nguyen, Golestani, Mehdi, Nguyen, Huu Tiep, Nguyen, Ngoc Anh, Fekih, Afef

    Published in Mathematics (Basel) (01-05-2023)
    “…This paper investigates the problem of output feedback attitude control for rigid spacecraft subject to inertia matrix uncertainty, space disturbance, and…”
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  10. 10

    Machine Learning Applications and Uncertainty Quantification Analysis for Reflood Tests by Tiep, Nguyen Huu, Kim, Kyung-Doo, Jeong, Hae-Yong, Xuan-Mung, Nguyen, Hoang, Van-Khanh, Ngoc Anh, Nguyen, Vu, Mai The

    Published in Applied sciences (01-01-2024)
    “…The reflooding phase, a crucial recovery process after a loss of coolant accident (LOCA) in reactors, involves cooling overheated fuel rods with subcooled…”
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  11. 11

    Study on Transmutation of Minor Actinides as Burnable Poison in VVER-1000 Fuel Assembly by Hoang, Van-Khanh, Nguyen, Huu Tiep, Tran, Hoai-Nam, Tran, Vinh Thanh, Ha, Pham Nhu Viet

    “…Thermal reactors have been considered as interim solution for transmutation of minor actinides recycled from spent nuclear fuel. Various studies have been…”
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  12. 12

    Comments on “Evaluation of neutron radiation damage in the VVER-1200 reactor pressure vessel” by Louis et al. [Radiat. Phys. Chem. 221 (2024): 111738] by Huu Tiep, Nguyen, Tran, Hoai-Nam

    “…•Some reused figures without citation in Louis et al. (2024).•Unavailable data were used in the VVER-1200 design.•An exaggerated statement was identified…”
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  13. 13

    Improvement in the accuracy of SPACE prediction for the unblocked FLECHT SEASET reflood tests by data assimilation by Tiep, Nguyen Huu, Kim, Kyung Doo, Heo, Jaeseok

    Published in Annals of nuclear energy (01-10-2021)
    “…•Nearly all the a posteriori quenching times reached the measured values.•The lower PCTs were strongly improved while the higher PCTs were slightly…”
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  14. 14

    Application of data assimilation in searching better lattice-physics parameters of fuel assembly by Tiep, Nguyen Huu, Kim, Kyung-Doo, Jeong, Hae-Yong, Anh, Nguyen Ngoc, Mung, Nguyen Xuan

    Published in Nuclear engineering and design (01-09-2023)
    “…•The data assimilation technique was applied to search the better candidates for fuel enrichment configurations.•The improvements were up to 0.1 w/o using the…”
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  15. 15

    STAR-CCM+ simulation of debris bed formation in the unheated DEFCON-S experiment by Eom, Jeong-Hyeon, Ra, In-Sik, Tak, Gi-Young, Tiep, Nguyen Huu, Jeong, Hae-Yong, Jung, Jae-Hoon, An, Sang-Mo

    Published in Annals of nuclear energy (01-10-2024)
    “…•The shape of debris bed is important for the coolability of molten corium in severe accident.•The debris bed formation in DEFCON-S experiment is analyzed with…”
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  16. 16