Contributors |
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xi | |
Preface |
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xv | |
Foreword |
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xvii | |
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1 | (20) |
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1.1 History of development of nuclear reactors |
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1 | (1) |
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1.2 Notable early nuclear reactors |
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1 | (4) |
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1.3 Growth of nuclear power |
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5 | (1) |
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1.4 Physics of nuclear safety |
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6 | (3) |
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1.5 Designing for safety of nuclear reactors |
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9 | (2) |
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1.6 Quantification of safety margins |
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11 | (3) |
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1.7 Role of CFD in safety assessment |
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14 | (3) |
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17 | (4) |
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19 | (2) |
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2 Computational fluid dynamics |
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21 | (218) |
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30 | (4) |
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2.2 Single-phase flow: Model equations |
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34 | (8) |
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2.3 Turbulence models for single-phase flows |
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42 | (48) |
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2.4 CFD modeling of multiphase flows |
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90 | (55) |
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2.5 Models for dense particulate flows |
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145 | (20) |
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165 | (74) |
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218 | (20) |
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238 | (1) |
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3 CFD model development for two-phase flows |
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239 | (98) |
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3.1 CFD analysis and prediction of boiling flows |
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242 | (20) |
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3.2 CFD modelling of boiling flows inside rod bundle |
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262 | (23) |
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3.3 Modelling of critical heat flux in BWRs: Role of CFD |
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285 | (17) |
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3.4 Modelling bubble dynamics in suppression pool using CFD |
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302 | (35) |
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323 | (1) |
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324 | (11) |
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335 | (2) |
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4 Evaluation of safety of light-water-cooled reactors using CFD |
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337 | (50) |
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337 | (1) |
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337 | (18) |
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4.3 CFD simulations for horizontal stratified two-phase flows |
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355 | (20) |
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4.4 Capability of CFD codes |
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375 | (1) |
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375 | (12) |
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375 | (1) |
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376 | (8) |
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384 | (2) |
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386 | (1) |
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5 Design of passive safety systems for advanced reactors using CFD |
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387 | (100) |
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5.1 Introduction to passive safety systems |
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390 | (3) |
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5.2 CFD requirement for simulation of passive systems |
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393 | (1) |
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5.3 Modeling of natural convection phenomena using CFD---Issues and challenges |
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394 | (7) |
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5.4 Design of passive residual heat removal system (PRHRS) using CFD |
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401 | (27) |
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5.5 Design of passive moderator cooling system using CFD |
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428 | (22) |
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5.6 Design of passive air-cooled condensers using CFD |
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450 | (8) |
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5.7 Design of Venturi scrubber for filtered containment venting system |
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458 | (19) |
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477 | (10) |
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481 | (4) |
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485 | (2) |
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6 Modelling of core melt scenarios in nuclear reactors |
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487 | (80) |
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6.1 Introduction to severe accident phenomena and progression in water-cooled reactors |
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489 | (4) |
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6.2 Current status of application of CFD codes for severe accidents |
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493 | (6) |
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6.3 Simulation of in-vessel retention of corium in PHWRs using CFD |
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499 | (25) |
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6.4 CFD simulation of debris bed coolability |
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524 | (15) |
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6.5 Modelling of melt coolability in ex-vessel conditions |
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539 | (19) |
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558 | (9) |
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561 | (4) |
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565 | (2) |
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7 Application of CFD for assessment of containment safety |
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567 | (96) |
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568 | (1) |
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7.2 Role of CFD in addressing containment safety issues |
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569 | (2) |
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7.3 Application of CFD for hydrogen distribution studies in post-accident containment atmospheres of Indian reactors |
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571 | (28) |
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7.4 Modelling of hydrogen recombination using CFD |
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599 | (17) |
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7.5 CFD modelling of hydrogen combustion for containment safety applications |
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616 | (25) |
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7.6 CFD analysis of hydrocarbon fireballs for safety assessment of nuclear power plants |
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641 | (12) |
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7.7 Conclusions and recommendations |
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653 | (2) |
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655 | (1) |
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656 | (7) |
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657 | (6) |
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8 Modeling of fire with CFD for nuclear power plants (NPPs) |
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663 | (66) |
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663 | (1) |
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8.2 Present and evolving scenario (industry specific scenario) |
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663 | (1) |
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8.3 Dynamic safety requirements |
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664 | (1) |
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8.4 Boundary for conventional fire modeling |
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664 | (1) |
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8.5 Fire modeling framework |
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664 | (1) |
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8.6 Design fire for industrial applications |
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665 | (1) |
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8.7 The understanding of flame and plume |
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666 | (2) |
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8.8 LES-based CFD procedure |
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668 | (4) |
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8.9 Plume puffing frequency |
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672 | (4) |
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8.10 Isothermal simulation for puffing |
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676 | (2) |
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678 | (1) |
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8.12 Oscillatory ceiling opening |
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679 | (1) |
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8.13 Ceiling opening with different aspect ratios |
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680 | (3) |
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8.14 Gravity currents for fire |
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683 | (6) |
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8.15 Ceiling opening with wall opening |
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689 | (1) |
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8.16 Fire and its characteristics |
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689 | (16) |
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8.17 Fire safety concern for Nuclear Power Plant |
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705 | (1) |
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8.18 The role of CFD in fire modeling |
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706 | (3) |
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8.19 Fire Hazard Analysis (FHA) using the strength of CFD for NPPS and allied facilities |
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709 | (1) |
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8.20 Methodology and technical basis |
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709 | (1) |
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8.21 Development of design fire |
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710 | (12) |
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722 | (7) |
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722 | (7) |
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9 Applications of computational fluid dynamics in design of sodium-cooled fast reactors |
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729 | (26) |
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729 | (2) |
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9.2 Thermal hydraulic characteristics of SFR |
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731 | (3) |
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9.3 Thermal hydraulic design limits |
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734 | (1) |
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9.4 CFD analysis requirements |
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734 | (1) |
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735 | (17) |
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752 | (3) |
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752 | (1) |
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753 | (2) |
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10 CFD and systems thermal-hydraulic analysis in the design and safety assessment of high-temperature reactors |
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755 | (46) |
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755 | (6) |
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10.2 Gas-cooled reactor analysis |
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761 | (15) |
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10.3 Molten salt-cooled reactor analysis |
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776 | (13) |
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10.4 Industrial perspective |
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789 | (4) |
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10.5 Summary and conclusions |
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793 | (8) |
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794 | (7) |
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11 Heat transfer and computational fluid dynamics for molten salt reactor technologies |
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801 | (34) |
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801 | (2) |
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11.2 Molten salts as heat transfer coolant |
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803 | (2) |
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11.3 Figures of merit development for coolant thermal-hydraulic performance |
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805 | (8) |
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11.4 Convective heat transfer correlations in molten salts |
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813 | (3) |
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11.5 CFD applications for MSR technologies |
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816 | (8) |
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11.6 MSR technical challenges |
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824 | (2) |
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826 | (9) |
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826 | (1) |
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826 | (3) |
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829 | (6) |
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12 Conclusions and future recommendation |
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835 | (16) |
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12.1 Simulation of single-phase turbulent flows in nuclear reactors |
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836 | (3) |
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12.2 Simulation of multiphase flows |
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839 | (4) |
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12.3 Role of Prandtl number Pr |
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843 | (1) |
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12.4 Relationship between flow pattern and design |
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844 | (1) |
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12.5 Multiscale modelling |
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844 | (1) |
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12.6 Current status of CFD validation through experiments |
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845 | (6) |
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846 | (5) |
Index |
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851 | |