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bunkers dohowever showsigns of cracking, which requires

very strict monitoring.

Examination of the periodic safety review, for which the

complete file was transmitted in June 2013, and of the

stress tests, is continuing. In 2016, ASNwill specify the

preconditions for continued operation.

1.2.6 Waste and effluent storage and

treatment facilities

The CEAwaste and effluent storage and treatment facilities

are addressed in chapter 16.

1.2.7 Installations undergoing decommissioning

The CEA facilities undergoing decommissioning, as well

as the CEA decommissioning strategy, are covered in

chapter 15.

1.3 Planned facilities

The purpose of the ASTRID project (Advanced Sodium

Technological Reactor for Industrial Demonstration),

currently at the design phase, is to produce a

technological demonstrator for which the technical

options can be extrapolated to a possible Generation IV

electricity generating reactor by about 2050. This

project is supported by CEA, in association with EDF

and Areva. Astrid is a Sodium-Cooled fast neutron

Reactor (SCR), one of the six identified Generation IV

reactor series. The first orientations envisaged for the

design of Astrid were presented in a Safety Guidelines

Document (DOrS) which was submitted to ASN in

2012 in advance of the regulatory procedures. This

DOrS precedes the optional transmission of a Safety

Options File (DOS) which was not transmitted before

the end of 2015, as had been initially planned by CEA.

This DOrS is also well upstream of the BNI creation

authorisation application procedure. Concerning this

DOrS, in a letter dated 10th April 2014, ASN informed

CEA of the demonstrations that would need to be

provided in the next stage of the procedure, so that

it could issue a position statement on the safety of

the Astrid project. For ASN, this reactor must offer a

level of safety at least equivalent to that of the third

generation reactors (the EPR in France), incorporate the

improvements resulting from the lessons learned from

the Fukushima Daiichi accident and, as a prototype of

a fourth generation plant series designed to provide

significant safety gains, enable reinforced safety options

to be prepared and tested.

1.4 ASN’s general assessment

of CEA actions

The results of 2015 and ASN’s assessment of each facility

are detailed per region in chapter 8, in chapter 15 for

the facilities being decommissioned and in chapter 16

for the waste processing and storage facilities.

2015 was marked by CEA being required to implement

post-Fukushima “hardened safety cores” in some of

its centres and facilities. This implementation will

significantly improve safety and enable CEA to acquire

robust diagnosis and emergency management resources.

ASNunderlined that the performance of these numerous

reviews associated with the preparation of the final

shutdown anddecommissioning authorisation application

files represents a major safety issue, which will require

significant resources on the part of CEA. CEA’s compliance

with the deadlines set for its “major commitments” has

improved. It also agreed to give fresh impetus to this

approach in order to share themain nuclear safety issues

to be dealt with over the coming decade.

ASN will also be vigilant with regard to the actual

initiation of the decommissioning operations on the

facilities finally shut down, in accordance with French

regulations (see chapter  15) and the updating of CEA’s

decommissioning, post-operational clean-out and waste

management strategy.

ASN considers that the level of safety in the facilities

operated by CEA is on the whole satisfactory, in

particular the operation of its experimental reactors.

ASN considers that CEA must reinforce its surveillance

and its oversight of external contractors in a context

of large-scale subcontracting.

2. NON-CEA NUCLEAR RESEARCH

INSTALLATIONS

2.1 Large National Heavy Ion

Accelerator

The Ganil (National Large Heavy Ion Accelerator)

economic interest group, was authorised by the Decree

of 29th December 1980 to create an accelerator in Caen

(BNI 113). This research facility produces, accelerates

and distributes ion beams with various energy levels

to study the structure of the atom. The intense, high-

energy beams produce strong fields of ionising radiation,

activating the materials in contact, which then emit

radiation even after the beams have stopped. Irradiation

thus constitutes the main risk at the Ganil.

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CHAPTER 14:

NUCLEAR RESEARCH AND MISCELLANEOUS INDUSTRIAL FACILITIES

ASN report on the state of nuclear safety and radiation protection in France in 2015