EURISOL R&D projects Kick-off meeting Pb/Bi loop target Thursday 10 th of May 2012 A. MARCHIX & V. BLIDEANU/CEA collaboration with AP.Bernardes & J.Vollaire/CERN.

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Presentation transcript:

EURISOL R&D projects Kick-off meeting Pb/Bi loop target Thursday 10 th of May 2012 A. MARCHIX & V. BLIDEANU/CEA collaboration with AP.Bernardes & J.Vollaire/CERN Licensing and safety aspects of the Pb/Bi loop target prototype development

Outline -Context -IRFU/LENAC &CERN collaboration -Methodology -Conclusion

CONTEXT The development of a new molten Pb/Bi ISOLDE target loop is a part of the EURISOL project which aims to develop the “next- generation” European ISOL radioactive ion beam (RIB) facility.EURISOL Several options have been identified for the 100KW liquid-metal target for the EURISOL project  A Molten Pb/Bi target may be an option Photograph of the 100 KW liquid-metal loop setup at IPUL

CONTEXT Safety studies for the development of a new Molten PB/Bi target should be used to :  Facilitate the future licensing process Compile data which may be used for a licensing process in future  Develop a Safe target and appropriate installation Safety expertise should be developed during OFF-Line development of the target in order to better assess the ON-LINE failure consequences

CONTEXT What do we know?  Liquid-metal target failure  containment must be guaranteed in order to avoid dispersion of radiological contaminants  failure scenario must be studied  Special care has to be taken concerning gas production/release and dispersion of contamination (Polonium and Astatine) What do we need ? -Safety studies and risk analysis specific to an ISOLDE liquid-Metal loop target New in FLUKA: model is now able to predict interaction of secondary α which can produced dangerous radioisotopes (α,Bi)  At and (α,Pb)  Po Acknowledgment to Alfredo Ferrari

COLLABORATION How to achieve it ? A collaboration has been signed between CEA/IRFU/LENAC and CERN in order to perform various safety studies such as: -Failure analysis of the molten Pb/Bi target -Risk assessments during development/production/operation/p ost-mortem -Fire study -Licensing documentation -Dismantling study of the molten Pb/Bi target (cost estimation) -Waste study Feed-back from PSI (MEGAPIE) and IPUL (liquid metal-loop) experience will be very welcome ! In collaboration of J.Vollaire DGS/RP

COLLABORATION Appropriate inputs for : safety integration, future licensing or safety file at CERN Expertise from other institutes CERN ISOLDE target and safety expertise CEA IRFU/LENAC Licensing and safety studies expertise

Nuclear safety principles General nuclear safety objective: To protect individuals, society and the environment by establishing and maintaining in nuclear power plants an effective defence against radiological hazard. Technical nuclear safety objectives  To prevent with high confidence accidents in nuclear plants;  To ensure that, for all accidents taken into account in the design of the plant, even those of very low probability, radiological consequences, if any, would be minor;  And to ensure that the likelihood of severe accidents with serious radiological consequences is extremely small. IAEA INSAG - 3

In France Nuclear safety and Transparency Act of June 2006 Objectives  Juridical framework on “civil” nuclear activities  Clarify and reinforce controls system and sanctions Main contribution ASN founding : nuclear safety independent authority CEA is the historical actor in nuclear safety (up to 1973)  Many different nuclear facilities (experimental reactor, accelerator...): huge nuclear safety culture  Research and development on nuclear safety  Permanent expert group Nuclear safety frame of reference, methodology document, expert department assistance

Nuclear safety framework To secure nuclear safety function:  control the confinement of radioactivity  control the limitation of exposure  control the reactivity  control the gas produced by radiolysis  control the cooling Unacceptable area Normal operation or abnormal condition Severe conditions within the design basis Residual risk Radiological impact Risk frequency Risks Radiation Exposure Confinement of radiological materials Human factor Fire hazard Cryogenic, pressure and vacuum hazard Anoxia Chemical hazard Electrical and magnetic field Mechanical hazard Dismantling External hazard... Concept of the defence in depth is applied to analyse each risk and perform a safety process Risk frequency is based on the feedback experiment

Concept of defence in depth Principle  to compensate for potential human and component failures  to maintain the effectiveness of the barriers by averting damage to the plant and to the barriers themselves  to protect the public and the environment from harm in the event that these barriers are not fully effective. Undesirable event Failure tree Failure mode of a safety function Barrier Failure

Last safety report accepted by ASN Detector located at 7m from reactor core IAEA is interested in in the feasibility of using detection of antineutrinos for safeguards purposes: monitoring reactor operation to detect possible unreported plutonium production Target: 0.85 m 3 Gd-Liquid scintillator (0.5%) Important risk of fire and explosion NUCIFER project (antineutrinos detector) implanted in OSIRIS experimental reactor LENAC contribution: the complete risk analysis the radiological impact evaluation the safety report the fire hazard study using CEA’s software (CEA fire expert validation)

Example of fire hazard assessment for Nucifer project Detector is isolated from ignition source by a wall to prevent fire risk detector wall Electronic and electricity Evaluation of the wall thickness according to the conservative fire source Simulation of the increasing temperature with time versus different wall thicknesses

Methodology on classical risk assessment Each risk from MOSAR list is quantified with respect to frequency and gravity Acceptable risk Risk as low as possible Unacceptable risk area MES : CEA software to assist security manager in facility operation project described step by step risk identified from MOSAR list quantification of each risk barriers added according to quantification of the risk

Example on classical risk assessment LOA : laser facility with radioprotection risk regulatory framework of the facility risk analysis Study of the access control of the laser room Double Chooz : neutrino detectors installation on the EDF reactor site of Chooz (2*1450 MW). 2*200 m 3 liquid scintillator. Environment protection report Source transfer and exploitation report Water environment protection report Reports submitted to ASN

Present studies related to safety CILEX APOLLON: 10 PW laser beam interaction with matter in order to study plasma properties IFMIF (accelerator): neutron production facility for studies on irradiation effect on material which will be used in future fusion reactor Radioprotection calculations (building design, ALARA optimisation for maintenance) Involvement in the licensing process in collaboration with Japanese team (host) SPIRAL2 phase1 (accelerator): heavy ion (S3) and neutron (NFS) beam for fundamental research Radioprotection calculations (building design, ALARA optimisation for maintenance, technical process choice) Classical risks Radioprotection Clearance historical waste Nuclear safety

Conclusion - A collaboration has been signed between CEA/IRFU/LENAC and CERN EN/STI/RBS to bring complementary safety expertise on board on both aspects safety analyses and licensing, in collaboration with DGS/RP - Feed-back from PSI and IPUL will be very welcome to learn from their past experienced