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COMPLEX FLUID FLOW IN POWER NUCLEAR REACTORS CORE; CASES OF BWR, PBMR AND HTR-PM

Yıl 2020, Cilt: 4 Sayı: 3, 25 - 34, 17.07.2020

Öz





In this work, the technology of PBMR, HTR-PM and BWR as well as the
nuclear reactor core constitution with fuel elements arrangement are presented.
The mathematical part: conservation equations for continuity, momentum and
energy as well as equations of state and boundary conditions, for both porous
media theory and two-phase flow theory are developed and applied to each type
of nuclear reactor. For the case of the HTR-PM and PBMR nuclear reactors, two
approaches cases are applied. The first approach is the study of a channel
saturated with a porous medium consisting of fuel spheres and cooled by an
inert gas, this to approach the HTR-PM. The second is an application for a case
of porous medium consisting of the same fuel spheres but arranged in an annular
domain to approach the PBMR. For the case of BWRs, a nuclear thermalhydraulic
channel is defined and the different two-phase flows presented. The same set-up
equation is applied except that it is written for each phase and for the
interface between the two phases, the specific case of annular two-phase flow
is studied. The obtained results, presented in figures and physically analyzed,
are very satisfactory. It can thus be concluded that applying the model of
porous media and the two-phase flow one for complex flows respectively for
PBMR, HTR-PM or BWR power nuclear reactors core can ensure a well behavior of
the nuclear reactor core thermalhydraulics. Some of presented results in this
paper were published or under full publication. 




Kaynakça

  • [1] Xu Wei, Sun Jun, Zheng Yanhua, Shi Lei, 2017, The influence of nuclear graphite oxidation opn air accident of HTR-PM, Annals of Nuclear Energy, 110 (2017) 1242-1248
  • [2] T.Dudley, W. Bouwer, P. de Villiers, Z. Wang, 2008, The Thermal–Hydraulic model for the pebble bed modular reactor (PBMR) plant operator training simulator system, Nuclear Engineering and Design, 238 (2008) 3102–3113
  • [3] V. N. Shah, and P. E. MacDonald, 1993, Aging and Life Extension of Major Light Water Reactor Components. Atlanta, GA: Elsevier Science, ISBN: 9780444894489.
  • [4] J.G. Collier and J. R. Thome, “Convective boiling and condensation”, Oxford Science Publications, troisième Edition, 1994.
  • [5] M. Bounar, A. Necir, K. Sidi-Ali, Kh. Bouhadef, 2019, Heat transfer evolution in a porous medium; dynamic and thermal fields calculations for high temperature nuclear reactors, Algerian Congress of Mechanics, Ghardaia, Algeria
  • [6] Bejan, (2004) Convection Heat Transfer, Wiley, New York, Chapter 12.
  • [7] W. Kays, M. Crawford, B. Weigand (2005) Convective Heat and Mass Transfer, McGraw Hill, New York, pp. 91–92.
  • [8] A. Necir, M. Bounar, K. Sidi-Ali, Kh. Oukil, Kh. Bouhadef, Analytical approach of forced convection in a porous channel, under evaluation for publication, 2019
  • [9] I. Yasri, M. A. Alreme, K. Sidi-Ali, A. Boumedien, 2014, Prédiction de la Chute de Pression et du Transfert de Chaleur Dans un Ecoulement à Deux Phases Annulaire Ascendant, Journées de Mécanique, EMP Bordj El Bahri
  • [10] G.B. Wallis, One-dimensional Two-phase Flow, McGraw-Hill, New York, 1969.
  • [11] G. F. Hewitt, N.S Hall-Taylor, “Annular Two-Phase Flow”, Pergamon, New York, 1970
Yıl 2020, Cilt: 4 Sayı: 3, 25 - 34, 17.07.2020

Öz

Kaynakça

  • [1] Xu Wei, Sun Jun, Zheng Yanhua, Shi Lei, 2017, The influence of nuclear graphite oxidation opn air accident of HTR-PM, Annals of Nuclear Energy, 110 (2017) 1242-1248
  • [2] T.Dudley, W. Bouwer, P. de Villiers, Z. Wang, 2008, The Thermal–Hydraulic model for the pebble bed modular reactor (PBMR) plant operator training simulator system, Nuclear Engineering and Design, 238 (2008) 3102–3113
  • [3] V. N. Shah, and P. E. MacDonald, 1993, Aging and Life Extension of Major Light Water Reactor Components. Atlanta, GA: Elsevier Science, ISBN: 9780444894489.
  • [4] J.G. Collier and J. R. Thome, “Convective boiling and condensation”, Oxford Science Publications, troisième Edition, 1994.
  • [5] M. Bounar, A. Necir, K. Sidi-Ali, Kh. Bouhadef, 2019, Heat transfer evolution in a porous medium; dynamic and thermal fields calculations for high temperature nuclear reactors, Algerian Congress of Mechanics, Ghardaia, Algeria
  • [6] Bejan, (2004) Convection Heat Transfer, Wiley, New York, Chapter 12.
  • [7] W. Kays, M. Crawford, B. Weigand (2005) Convective Heat and Mass Transfer, McGraw Hill, New York, pp. 91–92.
  • [8] A. Necir, M. Bounar, K. Sidi-Ali, Kh. Oukil, Kh. Bouhadef, Analytical approach of forced convection in a porous channel, under evaluation for publication, 2019
  • [9] I. Yasri, M. A. Alreme, K. Sidi-Ali, A. Boumedien, 2014, Prédiction de la Chute de Pression et du Transfert de Chaleur Dans un Ecoulement à Deux Phases Annulaire Ascendant, Journées de Mécanique, EMP Bordj El Bahri
  • [10] G.B. Wallis, One-dimensional Two-phase Flow, McGraw-Hill, New York, 1969.
  • [11] G. F. Hewitt, N.S Hall-Taylor, “Annular Two-Phase Flow”, Pergamon, New York, 1970
Toplam 11 adet kaynakça vardır.

Ayrıntılar

Birincil Dil İngilizce
Konular Metroloji,Uygulamalı ve Endüstriyel Fizik
Bölüm Research Articles
Yazarlar

Kamel Sidi-ali

Yayımlanma Tarihi 17 Temmuz 2020
Yayımlandığı Sayı Yıl 2020 Cilt: 4 Sayı: 3

Kaynak Göster

APA Sidi-ali, K. (2020). COMPLEX FLUID FLOW IN POWER NUCLEAR REACTORS CORE; CASES OF BWR, PBMR AND HTR-PM. Acta Materialia Turcica, 4(3), 25-34.
AMA Sidi-ali K. COMPLEX FLUID FLOW IN POWER NUCLEAR REACTORS CORE; CASES OF BWR, PBMR AND HTR-PM. ACTAMAT. Temmuz 2020;4(3):25-34.
Chicago Sidi-ali, Kamel. “COMPLEX FLUID FLOW IN POWER NUCLEAR REACTORS CORE; CASES OF BWR, PBMR AND HTR-PM”. Acta Materialia Turcica 4, sy. 3 (Temmuz 2020): 25-34.
EndNote Sidi-ali K (01 Temmuz 2020) COMPLEX FLUID FLOW IN POWER NUCLEAR REACTORS CORE; CASES OF BWR, PBMR AND HTR-PM. Acta Materialia Turcica 4 3 25–34.
IEEE K. Sidi-ali, “COMPLEX FLUID FLOW IN POWER NUCLEAR REACTORS CORE; CASES OF BWR, PBMR AND HTR-PM”, ACTAMAT, c. 4, sy. 3, ss. 25–34, 2020.
ISNAD Sidi-ali, Kamel. “COMPLEX FLUID FLOW IN POWER NUCLEAR REACTORS CORE; CASES OF BWR, PBMR AND HTR-PM”. Acta Materialia Turcica 4/3 (Temmuz 2020), 25-34.
JAMA Sidi-ali K. COMPLEX FLUID FLOW IN POWER NUCLEAR REACTORS CORE; CASES OF BWR, PBMR AND HTR-PM. ACTAMAT. 2020;4:25–34.
MLA Sidi-ali, Kamel. “COMPLEX FLUID FLOW IN POWER NUCLEAR REACTORS CORE; CASES OF BWR, PBMR AND HTR-PM”. Acta Materialia Turcica, c. 4, sy. 3, 2020, ss. 25-34.
Vancouver Sidi-ali K. COMPLEX FLUID FLOW IN POWER NUCLEAR REACTORS CORE; CASES OF BWR, PBMR AND HTR-PM. ACTAMAT. 2020;4(3):25-34.