スーパーフェニックス高速増殖炉<br>Superphenix : Technical and Scientific Achievements

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スーパーフェニックス高速増殖炉
Superphenix : Technical and Scientific Achievements

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  • 製本 Hardcover:ハードカバー版/ページ数 342 p.
  • 言語 ENG
  • 商品コード 9789462392458
  • DDC分類 539

Full Description

For the first time a book has been written on the technological and scientific knowledge, acquired during, buiding , operation and even dismantling of the Superphenix plant. This reactor remains today the most powerful sodium fast breeder reactor operated in the world.(1200 MWe). The last fast breeder reactor operated in the world is BN 800 in Russia that reached his nominal power (800 MWe) in 2016. 
Joel Guidez began his career in the field of sodium-cooled fast reactors after leaving Ecole Centrale-Paris, in 1973. He has held various positions at Cadarache, Phenix and Superphenix, including as the head of the thermal hydraulic laboratory conducting tests for Phenix, Superphenix and the EFR European Fast Reactor project. He was also head of the OSIRIS research reactor, located at SACLAY, and of the HFR European Commission reactor, located in the Netherlands and spent two years as nuclear attaché at the French embassyin Berlin. His 2012 book "Phenix: the experience feedback" was translated into English and republished in 2013, and this new book on Superphenix is in the same spirit of thematic analysis of a reactor experience feedback.

Gérard Prêle graduated from the Ecole Centrale-Lyon and entered EDF and the field of sodium-cooled fast reactors in 1983. In 1985 he joined Superphenix, where he was a duty engineer and was later in charge of safety. He has held various positions at Superphenix and Phenix and was a fast neutron reactor (SFR) engineer at the EDF Centre Lyonnais d'Ingénierie (CLI).  He worked  as Safety Security Environment and Radiation Protection Mission head in Superphenix  at the beginning of dismantling and then in the field of PWR for two years. Since 2006 he has been involved in the Gen IV and the SFR/Astrid projects. Today, as an SFR/system and operations expert, one of his major roles is assisting the CEA in the preliminary design of the ASTRID reactor.

Contents

1.General description.- 2.Construction review.- 3.Start-up trials.- 4.Objectives and operating results.- 5.Safety.- 6.Operating Experience.- 7.Fuel sub-assembly.- 8.Neutronics.- 9.The Primary pumps.- 10.Secondary sodium pumps and circuits.- 11.The intermediate heat exchangers.- 12.The steam generators.- 13.Sodium/water reaction.- 14.Sodium leaks and fires.- 15.Reactor shutdown and control systems.- 16.Residual power removal.-17.The materials.- 18.Hydraulics and thermohydraulics.- 19.In-Service Inspection.- 20.The chemistry.- 21.Sodium technology.- 22.The handling.- 23.The environmental results.- 24.The dismantling experience.- 25.Superphenix Children.- 26.Conclusion.

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