Complementary-safety-assessments-french-nuclear-safety

- 210 - 4.3. Facilities in the nuclear fuel cycle (La Hague, Tricastin, Mélox, FBFC)....................................282 4.3.1 Tricastin site................................................................................................................................. 282 4.3.2. La Hague site.............................................................................................................................. 283 4.3.3. Other facilities in the fuel cycle (Mélox, FBFC)........................................................................ 283 4.4. Other facilities (ATPu and Masurca)...........................................................................................283 4.4.1. ATPu...........................................................................................................................................283 4.4.2. Masurca.......................................................................................................................................283 5. LOSS OF THE ELECTRICAL POWER SUPPLIES AND COOLING SYSTEMS...........284 5.1. Experimental reactors............................................................................................................284 5.1.1. CEA reactors (Osiris, JHR, Phénix)............................................................................................ 284 5.1.2. Reactor operated by the ILL....................................................................................................... 292 5.2. Facilities in the nuclear fuel cycle (La Hague, Tricastin, Mélox, FBFC)..............................294 5.2.1. Tricastin site................................................................................................................................ 294 5.2.2. La Hague site.............................................................................................................................. 295 5.3. Other facilities (ATPu, Masurca)...........................................................................................304 5.3.1. ATPu...........................................................................................................................................304 5.3.2. Masurca.......................................................................................................................................305 6. SEVERE ACCIDENT MANAGEMENT.................................................................................307 6.1. Emergency management organisation and general provisions..............................................307 6.1.1. CEA facilities (experimental reactors, Masurca et ATPu).......................................................... 307 6.1.2. The reactor operated by the ILL................................................................................................. 309 6.1.3. Facilities of the nuclear fuel cycle.............................................................................................. 310 6.1.4. Conclusion..................................................................................................................................316 6.2. Severe accident management per facility...............................................................................316 6.2.1. Experimental reactors................................................................................................................. 316 6.2.2. Reactor operated by the ILL....................................................................................................... 322 6.2.3. Facilities of the nuclear fuel cycle.............................................................................................. 326 6.2.4. Other facilities............................................................................................................................ 330 7. CONDITIONS FOR USE OF OUTSIDE CONTRACTORS.................................................333 7.1. AREVA..................................................................................................................................333 7.2. CEA.......................................................................................................................................338 7.3. ILL.........................................................................................................................................340 8. CONCLUSION ........................................................................................................................... 342 8.1. General evaluation.................................................................................................................342 8.2. Safety implications ................................................................................................................342 8.3. Improving the robustness of facilities and forthcoming works..............................................343 REFERENCES .................................................................................................................................. 347

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