Multiphase Flow Dynamics 4 : Nuclear Thermal Hydraulics
Volume 4 of the successful book package "Multiphase Flow" is devoted to nuclear thermal hydraulics which is a substantial part of nuclear reactor safety. It provides knowledge and mathematical tools for adequate description of the process of transferring the fission heat released in materi...
Enregistré dans:
| Auteur principal: | |
|---|---|
| Format: | Livre numérique |
| Langue: | Anglais |
| Publié: |
Berlin, Heidelberg :
Springer Berlin Heidelberg
[20..].
Cham : Springer Nature |
| Accès en ligne: | Accès sur la plateforme de l'éditeur Accès sur la plateforme Istex Accès Université d'Orléans Accès INSA CVL |
| Note: |
Archives Springer e-books (Licence nationale) Archives Springer e-books (Licence nationale) |
| Autres localisations: | Voir dans le Sudoc |
| Edition sous un autre format: | • Multiphase flow dynamics, 4, Nuclear thermal hydraulics, Nikolay I. Kolev, Berlin, Springer, 2009, 1 vol. (XXXIII-745 p.), 978-3-540-92917-8 |
| LEADER | 05120nam a22003017a 4500 | ||
|---|---|---|---|
| 001 | 941708 | ||
| 008 | 090903q2000 xx ||| |||| 00| 0 eng d | ||
| 009 | PPN136305741 | ||
| 020 | |a 9783540929185 | ||
| 041 | 0 | |a eng | |
| 082 | |a 620.1064 | ||
| 100 | 1 | |a Kolev, Nikolay Ivanov, |d 1951-...., |c ingénieur. | |
| 245 | 1 | 0 | |a Multiphase Flow Dynamics 4 : |b Nuclear Thermal Hydraulics |c by Nikolay Ivanov Kolev. |
| 260 | |a Berlin, Heidelberg : |b Springer Berlin Heidelberg. | ||
| 260 | |a Cham : |b Springer Nature, |c [20..]. | ||
| 500 | |a Archives Springer e-books (Licence nationale) | ||
| 500 | |a Archives Springer e-books (Licence nationale) | ||
| 505 | 1 | |a Heat release in the reactor core Temperature inside the fuel elements The #x201C;simple#x201D; steady boiling flow in a pipe The #x201C;simple#x201D; steady three-fluid boiling flow in a pipe Core thermal hydraulic Flow boiling and condensation stability analysis Critical multiphase flow Steam generators Moisture separation Pipe networks Some auxiliary systems Emergency condensers Core degradation Melt-coolant interaction Coolability of layers of molten reactor material External cooling of reactor vessels during severe accident Thermo-physical properties for severe accident analysis | |
| 506 | |a Accès en ligne pour les établissements français bénéficiaires des licences nationales | ||
| 506 | |a Accès soumis à abonnement pour tout autre établissement | ||
| 506 | |a Conditions particulières de réutilisation pour les bénéficiaires des licences nationales. https://www.licencesnationales.fr/springer-nature-ebooks-contrat-licence-ln-2017 | ||
| 520 | |a Volume 4 of the successful book package "Multiphase Flow" is devoted to nuclear thermal hydraulics which is a substantial part of nuclear reactor safety. It provides knowledge and mathematical tools for adequate description of the process of transferring the fission heat released in materials due to nuclear reactions into its environment. It step by step introduces into the heat release inside the fuel, temperature fields in the fuels, the "simple" boiling flow in a pipe described using ideas of different complexity like equilibrium, non equilibrium, homogeneity, non homogeneity. Then the "simple" three-fluid boiling flow in a pipe is described by gradually involving the mechanisms like entrainment and deposition, dynamic fragmentation, collisions, coalescence, turbulence. All heat transfer mechanisms are introduced gradually discussing their uncertainty. Different techniques are introduced like boundary layer treatments or integral methods. Comparisons with experimental data at each step demonstrate the success of the different ideas and models. After an introduction into the design of the reactor pressure vessels for pressurized and boiling water reactors the accuracy of the modern methods is demonstrated using large number of experimental data sets for steady and transient flows in heated bundles. Starting with single pipe boiling going through boiling in a rod bundles the analysis of complete vessel including the reactor is finally demonstrated. Then powerful method for non-linear stability analysis of flow boiling and condensation is introduced. Models are presented and their accuracies are investigated for describing critical multiphase flow at different level of complexity. Basics of designing of steam generators, moisture separators and emergency condensers are presented. Methods for analyzing a complex pipe network flows with components like pumps, valves etc. are also presented. Methods for analysis of important aspects of the severe accidents like melt-water interactions, external cooling and cooling of layers of molten nuclear reactor material are presented. Valuable sets of thermo-physical and transport properties for severe accident analysis are presented for the following materials: uranium dioxide, zirconium dioxide, stainless steel, zirconium, aluminum, aluminum oxide, silicon dioxide, iron oxide, molybdenum, boron oxide, reactor corium, sodium, lead, bismuth, and lead-bismuth eutectic alloy. The emphasis is on the complete and consistent thermo dynamical sets of analytical approximations appropriate for computational analysis. Therefore the book presents a complete coverage of the modern Nuclear Thermal Hydrodynamics | ||
| 776 | 0 | |0 137781199 |t Multiphase flow dynamics |h 4 |i Nuclear thermal hydraulics |f Nikolay I. Kolev |c Berlin |n Springer |d 2009 |p 1 vol. (XXXIII-745 p.) |z 978-3-540-92917-8 | |
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