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xi | |
About the editor |
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xiii | |
Preface of JSME Series in Thermal and Nuclear Power Generation |
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xv | |
Preface to Volume 7: Pressurized Heavy Water Reactors: CANDU |
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xvii | |
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1 Introduction. World energy production and the contribution of PHWRs |
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1 | (44) |
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1.1 Status of electricity generation in the world and selected countries |
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1 | (8) |
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1.2 Pressurized heavy water reactors: typical performance in Canada |
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9 | (2) |
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1.3 Current status, advantages, and challenges of nuclear-powered reactors |
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11 | (2) |
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1.4 Global operating reactor data |
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13 | (4) |
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1.5 The history and global context of pressurized heavy water reactors |
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17 | (4) |
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1.6 Pressurized heavy water reactors in operation |
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21 | (1) |
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1.7 Current activities in PHWRs, and modem nuclear power reactors and plants, including PWRs, BWRs, AGRs, LGRs, and SFRs |
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21 | (1) |
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1.8 Details on present and proposed pressurized heavy water reactors |
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21 | (9) |
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1.9 Summary of the pressurized heavy water reactor status and issues going forward |
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30 | (1) |
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1.10 Pressurized heavy water reactors immediate and future path |
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31 | (5) |
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36 | (1) |
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37 | (8) |
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Appendix: Additional pressurized heavy water reactor information sources |
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39 | (1) |
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40 | (5) |
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45 | (24) |
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2.1 Nuclear power reactors and their fuels |
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46 | (2) |
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2.2 Nuclear fuel materials |
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48 | (1) |
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2.3 Fuel-cladding material |
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49 | (1) |
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2.4 Fuel pellet, element, and assembly/bundle |
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50 | (3) |
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53 | (7) |
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2.6 Fuel failure mechanisms and fuel failures |
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60 | (1) |
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2.7 Fuel safety and acceptance criteria |
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61 | (2) |
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2.8 Advanced fuel concept |
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63 | (6) |
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67 | (1) |
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67 | (2) |
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3 Zr-2.5Nb pressure tubes in CANDU* reactors |
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69 | (66) |
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70 | (1) |
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3.2 Manufacturing background--resulting microstructural features-- microchemistry |
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71 | (6) |
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3.3 CANDU fuel channel design |
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77 | (3) |
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3.4 In-reactor deformation of pressure tubes |
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80 | (7) |
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3.5 Variability of pressure tubes |
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87 | (2) |
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3.6 Parameters affecting in-reactor deformation |
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89 | (15) |
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3.7 Mechanisms of irradiation-induced deformation |
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104 | (2) |
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3.8 Modeling pressure tube deformation |
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106 | (11) |
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3.9 Finite element methods |
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117 | (7) |
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124 | (11) |
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126 | (1) |
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126 | (9) |
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4 Computational modeling of in-reactor deformation in CANDU* fuel channels |
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135 | (36) |
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136 | (2) |
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4.2 Pressure tube deformation |
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138 | (3) |
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4.3 3D finite element analysis of in-reactor fuel channel deformation |
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141 | (10) |
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4.4 Finite element analysis output |
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151 | (7) |
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4.5 Comparison between 3D versus ID finite element analysis results |
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158 | (2) |
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4.6 3D finite element analysis results based on different fuel channel configurations |
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160 | (2) |
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4.7 Calibration of finite element model |
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162 | (3) |
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165 | (6) |
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167 | (1) |
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168 | (3) |
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5 Design and aging management for feeder pipe and feeder supports |
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171 | (58) |
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172 | (1) |
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5.2 Feeder design and bend manufacturing |
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173 | (16) |
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5.3 Operating experience of feeders |
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189 | (4) |
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193 | (29) |
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5.5 Practices for new feeders for refurbishment |
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222 | (7) |
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225 | (4) |
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229 | (46) |
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229 | (1) |
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6.2 General description of pressurized heavy water reactor steam generators |
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230 | (1) |
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6.3 Sizes of pressurized heavy water reactor steam generators, including comparison to pressurized water reactor steam generators |
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231 | (1) |
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6.4 History and evolution of pressurized heavy water reactor steam generators |
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232 | (2) |
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6.5 Design requirements and philosophy, high circulation ratio, conservative design limits |
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234 | (4) |
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6.6 Tube bundle sizing and configuration, including integral preheater designs |
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238 | (4) |
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6.7 Tube materials used in pressurized heavy water reactor steam generators |
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242 | (4) |
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6.8 Tube supports in pressurized heavy water reactor steam generators |
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246 | (2) |
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6.9 SteanjAvater separators |
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248 | (3) |
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6.10 Circulation, transient behavior, stability, and tube vibration |
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251 | (4) |
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6.11 Water chemistry and corrosion |
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255 | (3) |
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6.12 Performance, maintenance, and reliability |
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258 | (3) |
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6.13 Pressure boundary and manufacturing processes |
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261 | (7) |
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6.14 Replacement of pressurized heavy water reactor steam generators |
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268 | (3) |
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6.15 Application of pressurized heavy water reactor steam generator technology to pressurized water reactors |
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271 | (2) |
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273 | (2) |
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7 Electrical power systems |
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275 | (12) |
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276 | (1) |
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7.2 Design principles of a CANDU electrical power systems |
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276 | (1) |
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7.3 Plant electrical power systems overview |
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276 | (1) |
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277 | (1) |
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278 | (1) |
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279 | (1) |
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7.7 The emergency power supply system |
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279 | (2) |
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7.8 Alternate alternating current power supply in response to the Fukushima events |
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281 | (1) |
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7.9 Common and unit concepts in a multiunit station |
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282 | (1) |
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283 | (1) |
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7.11 Automatic transfer system |
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284 | (1) |
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7.12 Switchyard and synchronizing to the grid |
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285 | (1) |
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7.13 Highlights of this chapter |
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285 | (2) |
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286 | (1) |
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287 | (28) |
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287 | (2) |
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8.2 Core concepts for radiation protection |
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289 | (17) |
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8.3 Considerations for pressurized heavy water reactor radiation protection |
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306 | (6) |
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312 | (3) |
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312 | (1) |
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313 | (2) |
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9 Fitness for service and related concepts |
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315 | (14) |
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315 | (1) |
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9.2 Roots in Canadian standards and regulatory documents |
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316 | (1) |
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9.3 Definitions of key terms |
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317 | (2) |
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9.4 The continuum from design to decommissioning |
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319 | (1) |
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9.5 Steps in conducting a fitness for service assessment |
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320 | (1) |
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9.6 The perils of projections |
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321 | (3) |
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324 | (1) |
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9.8 How critical is configuration management? |
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325 | (1) |
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9.9 Limitations and traps in fitness for service declarations |
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326 | (3) |
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10 Fitness-for-service guidelines |
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329 | (58) |
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329 | (14) |
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343 | (7) |
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10.3 Steam generator tubes |
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350 | (17) |
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367 | (20) |
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382 | (1) |
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383 | (1) |
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383 | (4) |
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11 Overview of the Canadian Nuclear Safety Commission--Canada's nuclear regulator |
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387 | (12) |
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11.1 Canadian Nuclear Safety Commission's mandate and role |
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387 | (1) |
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11.2 Organizational structure |
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388 | (2) |
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11.3 Nuclear power plants |
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390 | (6) |
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11.4 Application of the regulatory framework |
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396 | (3) |
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398 | (1) |
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12 The extended operation and life extension project of Embalse Nuclear Power Plant--an account from a regulator's perspective |
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399 | (30) |
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12.1 First operating cycle |
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401 | (1) |
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12.2 Life extension decision |
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401 | (1) |
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402 | (1) |
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403 | (9) |
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12.5 Embalse's life extension |
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412 | (1) |
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12.6 General strategy for licensing |
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413 | (1) |
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12.7 Description of the life extension project |
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413 | (1) |
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12.8 Main refurbishment activities--licensing agreements and regulatory oversight |
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414 | (2) |
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12.9 Evolution of activities for the agreed licensing |
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416 | (1) |
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12.10 Planning and scheduling |
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416 | (1) |
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12.11 Organizational structure of the utility for refurbishment |
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416 | (1) |
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12.12 Condition assessments of the unit |
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417 | (1) |
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12.13 Environmental radiological impact assessment |
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417 | (1) |
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12.14 Environmental qualification program |
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418 | (1) |
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12.15 Agingmanagement program |
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418 | (1) |
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12.16 Management of design changes and improvements related to safety |
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418 | (2) |
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420 | (1) |
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12.18 Moderator heat exchangers replacement |
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420 | (1) |
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12.19 Severe accident management program |
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420 | (1) |
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12.20 Seismic reassessment |
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421 | (1) |
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421 | (1) |
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12.22 Steam generators replacement |
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422 | (2) |
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12.23 Training and certification of personnel |
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424 | (1) |
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12.24 Retum-to-service program |
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425 | (4) |
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13 Cernavoda--CANDU nuclear power plants in Romania |
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429 | (14) |
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13.1 Historical perspective |
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429 | (1) |
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13.2 Legislative and regulatory framework for nuclear safety in Romania |
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430 | (2) |
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13.3 Safety philosophy and defense-in-depth of the CANDU nuclear power plants |
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432 | (8) |
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13.4 Safety upgrades post-Fukushima |
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440 | (3) |
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441 | (2) |
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14 Pressurized heavy water reactors probabilistic safety assessment |
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443 | (34) |
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443 | (3) |
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14.2 Level 1 probabilistic safety assessment for internal events at full power |
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446 | (15) |
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14.3 Level 2 probabilistic safety assessment for internal events at full power |
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461 | (6) |
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14.4 Outage probabilistic safety assessment |
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467 | (3) |
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14.5 Internal fire probabilistic safety assessment |
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470 | (2) |
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14.6 Internal flood probabilistic safety assessment |
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472 | (1) |
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14.7 Seismic probabilistic safety assessment |
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473 | (1) |
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14.8 High Wind probabilistic safety assessment |
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474 | (3) |
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475 | (2) |
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15 Severe accident prevention and mitigation in pressurized heavy water reactors |
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477 | (32) |
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Samuel Hilton Gyepi-Garbrah |
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478 | (3) |
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15.2 Basic phenomena and behavior involving severe accident in pressurized heavy water reactors |
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481 | (4) |
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15.3 Pressurized heavy water reactors and accident progression core damage states |
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485 | (5) |
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15.4 Behavior and phenomena common and different from light water reactors and pressurized heavy water reactors |
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490 | (4) |
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15.5 Accident prevention in pressurized heavy water reactors |
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494 | (2) |
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15.6 Accident mitigation in pressurized heavy water reactors |
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496 | (4) |
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15.7 Severe accident management program in pressurized heavy water reactors |
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500 | (2) |
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15.8 Research, development, and challenges for the future of pressurized heavy water reactors |
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502 | (1) |
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502 | (7) |
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502 | (1) |
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503 | (6) |
Index |
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509 | |