Search Results - "Davilu, H."

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  1. 1

    Robust nonlinear model predictive control for nuclear power plants in load following operations with bounded xenon oscillations by Eliasi, H., Menhaj, M.B., Davilu, H.

    Published in Nuclear engineering and design (01-02-2011)
    “…▶ In this work, a robust nonlinear model predictive control algorithm is developed. ▶ This algorithm is applied to control the power level for load following…”
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    Journal Article
  2. 2

    Robust nonlinear model predictive control for a PWR nuclear power plant by Eliasi, H., Menhaj, M.B., Davilu, H.

    “…One of the important operations in nuclear power plants is power control during load following in which many robust constraints on both input and measured…”
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    Journal Article
  3. 3

    A numerical technique for analysis of transient two-phase flow in a vertical tube using the Drift Flux Model by Talebi, S., Kazeminejad, H., Davilu, H.

    Published in Nuclear engineering and design (2012)
    “…► A numerical technique for transient two-phase flow in a vertical channel using the Drift Flux Model is presented. ► The proposed model was validated for wide…”
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    Journal Article
  4. 4

    Prediction of dryout and post-dryout wall temperatures using film thickness model by Talebi, S., Kazeminejad, H., Davilu, H.

    Published in Nuclear engineering and design (01-03-2012)
    “…► An annular flow model of dryout heat transfer for flow boiling is presented. ► The model predictions have been tested against literature data from…”
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    Journal Article
  5. 5

    Adaptive estimator-based dynamic sliding mode control for the water level of nuclear steam generators by Ansarifar, G.R., Talebi, H.A., Davilu, H.

    Published in Progress in nuclear energy (New series) (01-04-2012)
    “…Steam Generator (SG) is a crucial component of nuclear power plant. The proper water level control of a nuclear steam generator is of great importance in order…”
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    Journal Article
  6. 6

    Gain scheduled dynamic sliding mode control for nuclear steam generators by Ansarifar, G.R., Davilu, H., Talebi, H.A.

    Published in Progress in nuclear energy (New series) (01-08-2011)
    “…U-Tube Steam Generator (UTSG) is one of the most important facilities in a pressurized-water nuclear reactor. Poor control of the Steam Generator (SG) water…”
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    Journal Article
  7. 7

    An adaptive-dynamic sliding mode controller for non-minimum phase systems by Ansarifar, G.R., Talebi, H.A., Davilu, H.

    “…► A novel systematic approach for designing an adaptive dynamic sliding manifold. ► A crucial step in dynamic sliding mode control. ► A big step forward in…”
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    Journal Article
  8. 8

    Adaptive fuzzy model based predictive control of nuclear steam generators by Eliasi, H., Davilu, H., Menhaj, M.B.

    Published in Nuclear engineering and design (01-03-2007)
    “…Poor control of U-tube steam generators (UTSG) in a nuclear power plant can lead to frequent reactor shutdowns or damage of turbine blades. The dynamics of…”
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    Journal Article
  9. 9

    Calculation of total effective dose equivalent and collective dose in the event of a LOCA in Bushehr Nuclear Power Plant by Raisali, G., Davilu, H., Haghighishad, A., Khodadadi, R., Sabet, M.

    Published in Radiation protection dosimetry (01-12-2006)
    “…In this research, total effective dose equivalent (TEDE) and collective dose (CD) are calculated for the most adverse potential accident in Bushehr Nuclear…”
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    Journal Article
  10. 10

    CYBPET: a cylindrical PET system for breast imaging by Karimian, A., Thompson, C.J., Sarkar, S., Raisali, G., Pani, R., Davilu, H., Sardari, D.

    “…We propose a Cylindrical Breast PET (CYBPET) system for breast imaging with patients in the prone position. An individual pendulous breast is covered by thin…”
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    Journal Article
  11. 11

    A dedicated PET system for breast imaging (CYBPET) by Karimian, A., Thompson, C.J., Sarkar, S., Raisali, G., Pani, R., Davilu, H., Sardari, D.

    “…Early detection of breast cancer is very important for efficient and effective treatment. Conventional whole body PET (WB-PET) scanners provide metabolic…”
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    Conference Proceeding
  12. 12

    Reliability evaluation of a natural circulation system by Jafari, Jalil, D’Auria, Francesco, Kazeminejad, Hossein, Davilu, Hadi

    Published in Nuclear engineering and design (01-09-2003)
    “…This paper discusses a reliability study performed with reference to a passive thermohydraulic natural circulation (NC) system, named TTL-1. A methodology…”
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    Journal Article
  13. 13

    Loss of coolant accident analyses on Tehran research reactor by RELAP5/MOD3.2 code by Hedayat, Afshin, Davilu, Hadi, Jafari, Jalil

    Published in Progress in nuclear energy (New series) (01-01-2007)
    “…In this paper, a loss of coolant accident (LOCA) in Tehran research reactor (TRR) is analyzed. The following procedure consists of three major parts. First, a…”
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    Journal Article