Published 1997 | Version v1
Report

Nuclear Fuel in France: an ever changing world - most recent safety concerns of DSIN

  • 1. Direction de la surete des installations nucleaires - DSIN, 99 Rue de Grenelle, 75353 Paris 07 SP (France)
  • 2. Direction regionale de l'industrie, de la recherche et de l'environnement - DRIRE de la Region Rhones Alpes, 146 Rue Pierre Corneille, 69426 Lyon Cedex 03 (France)

Description

The design and management of nuclear fuel have seen many changes in France the last few years. Such changes, brought about by the operating organisation, are essentially based on the increase of the fuel discharge burn up before unloading, the adoption of MOX fuel in reactors, and the improvement and diversification of nuclear fuel products (introduction of fuels of foreign origins, i.e. German, Spanish and Swedish). The French safety authority is not, a priori, opposed to these changes but it has to ensure that, at each step, identified safety problems are being analysed and resolved appropriately. New safety concerns arise in the whole fuel cycle: better care needs to be taken in the handling and transporting of high burn up fuels than fresh UO2 fuels, the use of MOX fuel demands the reinforcement of the radiation protection measures taken at all steps of the fuel cycle (manufacturing, handling during fabrication and in the reactor, transportation, reprocessing and disposal), and imposes a longer cooling period than UO2 fuel. After a comprehensive view of the main regulatory actions of the French nuclear safety authority, the DSIN, supported by the Institute for Nuclear Safety and Protection (IPSN) in the field of nuclear fuel, emphasizing its responsibilities versus those of the operating organisation in particular where the evolution of fuel is concerned, this present paper tries to roughly depict the most recent changes in management and design that affected the nuclear fuel loaded in French pressurized water reactors, such as GEMMES fuel management, penetration of MOX fuel, fuel product development, etc. It also intends to address some of the main current safety and regulatory issues associated with these changes

Part of:
Proceedings of the specialist meeting on nuclear fuel and control rods: operating experience, design evolution and safety aspects

Additional details

Publishing Information

ISBN
84-87275-78-8
Imprint Title
Proceedings of the specialist meeting on nuclear fuel and control rods: operating experience, design evolution and safety aspects
Imprint Pagination
420 p.
Journal Page Range
p. 65-79
Report number
NEA-CSNI-R--1997-2

Conference

Title
operating experience, design evolution and safety aspects
Acronym
Specialist meeting on nuclear fuel and control rods
Dates
5-7 Nov 1996
Place
Madrid (Spain)

Optional Information

Secondary number(s)
CSN-COE--10-06