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1 | (1) |
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1 | (1) |
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1 | (1) |
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2 | (1) |
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2 | (1) |
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2 Roles of System Codes and Computational Fluid Dynamics in the Nuclear Power Plant Design Process |
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2 | (2) |
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3 Activities Involving Computational Fluid Dynamics in Support of Nuclear Power Plant Design |
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4 | (11) |
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4 | (1) |
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5 | (2) |
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3.3 Code developers of computational fluid dynamics |
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7 | (2) |
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3.4 Research organizations |
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9 | (6) |
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4 Status of Verification and Validation for the Use of Computational Fluid Dynamics in Nuclear Power Plant Design |
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15 | (2) |
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15 | (1) |
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4.2 Validation gaps and issues involved |
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16 | (1) |
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5 Future Use of Computational Fluid Dynamics for Selected Reactor Types |
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17 | (8) |
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5.1 Supercritical water reactor |
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17 | (1) |
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5.2 Water-water energetic reactor |
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18 | (2) |
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5.3 Sodium cooled fast reactors |
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20 | (3) |
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5.4 Pressurized water reactors |
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23 | (2) |
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6 Best Practice Guidelines in the Use of Computational Fluid Dynamics for Nuclear Power Plant Design |
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25 | (9) |
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6.1 Best practice guidelines for safety analyses |
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25 | (2) |
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27 | (7) |
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7 Summary of Experimental Requirements for Producing Computational Fluid Dynamics Grade Data |
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34 | (2) |
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7.1 General experimental requirements |
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34 | (1) |
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7.2 Validation of two phase flow modelling for computational fluid dynamics |
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35 | (1) |
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36 | (5) |
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8.1 General requirements for practitioners of computational fluid dynamics |
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36 | (1) |
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8.2 Specific knowledge areas |
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36 | (1) |
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8.3 Summary of training courses in computational fluid dynamics for reactor design |
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37 | (4) |
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9 Uncertainty Quantification |
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41 | (11) |
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41 | (2) |
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9.2 Aspects of uncertainty quantification |
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43 | (5) |
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48 | (3) |
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51 | (1) |
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10 Gaps in Computational Fluid Dynamics Technology Applied to Nuclear Power Plant Design Issues |
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52 | (12) |
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10.1 Verification and validation |
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52 | (2) |
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10.2 Range of application of turbulence models |
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54 | (3) |
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10.3 Stratification and buoyancy effects |
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57 | (1) |
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10.4 Coupling system/computational fluid dynamics codes |
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57 | (4) |
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10.5 Coupling with other physics codes |
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61 | (1) |
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10.6 Computing power limitations |
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62 | (2) |
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64 | (3) |
References |
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67 | (10) |
Abbreviations |
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77 | (2) |
Contributors to Drafting and Review |
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79 | (1) |
Structure of the Iaea Nuclear Energy Series |
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80 | |