Using High Temperature Gas-Cooled Reactors for Energy...
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Experiments for each defence-in-depth level: legacy, in progress, and new ESFR-SMART: new Horizon-2020 project on SFR safety K. Mikityuk 1 , E. Girardi 2 , J. Krepel 1 , E. Bubelis 3 , E. Fridman 4 , A. Rineiski 3 , N. Girault 5 , F. Payot 6 , L. Buligins 7 , G. Gerbeth 4 , N. Chauvin 6 , C. Latge 6 , J.-C. Garnier 6 1 Paul Scherrer Institut (PSI), Villigen PSI, Switzerland 2 Électricité de France (EDF), Paris-Saclay, France 3 Karlsruhe Institute of Technology (KIT), Karlsruhe, Germany 4 Helmholtz-Zentrum Dresden-Rossendorf (HZDR), Dresden, Germany 5 Institut de Radioprotection et de Sûreté Nucléaire (IRSN), Saint-Paul-Lez-Durance, France 6 Commissariat à l'énergie atomique et aux énergies alternatives (CEA), Saint-Paul-Lez-Durance, France 7 Institute of Physics, University of Latvia (IPUL), Riga, Latvia IAEA –CN245-450 P1-46 To improve the public acceptance of the future nuclear power in Europe we have to demonstrate that the new reactors have significantly higher safety level compared to traditional reactors. The Horizon-2020 ESFR- SMART project (European Sodium Fast Reactor Safety Measures Assessment and Research Tools) aims at enhancing further the safety of Generation-IV SFRs and in particular of the commercial-size European Sodium Fast Reactor (ESFR) in accordance with the European Sustainable Nuclear Industrial Initiative (ESNII) roadmap and in close cooperation with the Advanced Sodium Technological Reactor for Industrial Demonstration (ASTRID) program. Summary Partners and relevant expertise IPUL: - AMPERE - TESLA HZDR: - DRESDYN KIT: - KASOLA - SOLTEC CEA: - CHEOPS - PAPIRUS Network of EU sodium facilities INPUT Legacy data OUTCOME Validated codes New data INPUT FP7 projects GIF ARDECo OUTCOME New ESFR concept SP1 Analytical assessment of new safety measures for ESFR SP3. Management and interactions WP1.3 Measures to prevent sodium boiling KIT WP1.4 Measures to prevent severe accidents HZDR WP1.5 Measures to mitigate severe accidents KIT SP2 R&D to support SFR safety enhancement WP2.2 New experiments for safety CEA WP2.3 European sodium facilities support IPUL WP2.4 Instrumentation for safety HZDR WP2.5 New measurements of fuel properties CEA WP1.2 Normal operation PSI WP1.1 New safety measures EDF WP2.1 Codes calibration and validation IRSN WP3.1 Dissemination, education and training CEA WP3.2 Project management PSI 1. Produce new experimental data in order to support calibration and validation of the computational tools for each defence-in-depth level. 2. Test and qualify new instrumentations in order to support their utilization in the reactor protection system. 3. Perform further calibration and validation of the computational tools for each defence-in-depth level in order to support safety assessments of Generation-IV SFRs, using the data produced in the project as well as selected legacy data. 4. Select, implement and assess new safety measures for the commercial-size ESFR, using the GIF methodologies, the FP7 CP-ESFR project legacy, the calibrated and validated codes and being in accordance with the update of the European and international safety frameworks taking into account the Fukushima accident. 5. Strengthen and link together new networks, in particular, the network of the European sodium facilities and the network of the European students working on the SFR technology. Objectives KASOLA SPX KNS-37 SOLTEC CABRI SCARABEE JOLO LIVE MOCKA CHUG FAUST NALA FANAL MOX fuel properties measurements Eddy-Current Flow Meter development Starting ESFR design The new project on Generation-IV Sodium Fast Reactor safety starts September 1, 2017 and ends on August 31, 2021. The project has received funding from the Euratom research and training programme 2014-2018 under grant agreement No 754501 Conclusions Experience from EU projects related to SFR safety New SFR safety- related tests Sodium facilities & instrumentation Experience in SFR operation Past SFR safety related tests Experience in SFR licensing SFR safety-related education ARDECo SFR fuel measurements
Transcript of Using High Temperature Gas-Cooled Reactors for Energy...
Experiments for each defence-in-depth level: legacy, in progress, and new
ESFR-SMART: new Horizon-2020 project on SFR safety
K. Mikityuk1, E. Girardi2, J. Krepel1, E. Bubelis3, E. Fridman4, A. Rineiski3, N. Girault5, F. Payot6, L. Buligins7, G. Gerbeth4, N. Chauvin6, C. Latge6, J.-C. Garnier6
1Paul Scherrer Institut (PSI), Villigen PSI, Switzerland 2Électricité de France (EDF), Paris-Saclay, France
3Karlsruhe Institute of Technology (KIT), Karlsruhe, Germany 4Helmholtz-Zentrum Dresden-Rossendorf (HZDR), Dresden, Germany
5Institut de Radioprotection et de Sûreté Nucléaire (IRSN), Saint-Paul-Lez-Durance, France 6Commissariat à l'énergie atomique et aux énergies alternatives (CEA), Saint-Paul-Lez-Durance, France
7Institute of Physics, University of Latvia (IPUL), Riga, Latvia
IAEA –CN245-450 P1-46
To improve the public acceptance of the future nuclear power in Europe we have to demonstrate that the new reactors have significantly higher safety level compared to traditional reactors. The Horizon-2020 ESFR-SMART project (European Sodium Fast Reactor Safety Measures Assessment and Research Tools) aims at enhancing further the safety of Generation-IV SFRs and in particular of the commercial-size European Sodium Fast Reactor (ESFR) in accordance with the European Sustainable Nuclear Industrial Initiative (ESNII) roadmap and in close cooperation with the Advanced Sodium Technological Reactor for Industrial Demonstration (ASTRID) program.
Summary Partners and relevant expertise
IPUL:- AMPERE- TESLA
HZDR:- DRESDYN
KIT:- KASOLA- SOLTEC
CEA:- CHEOPS- PAPIRUS
Network of EU sodium facilities INPUT
Legacy data
OUTCOMEValidated codes
New data
INPUTFP7 projects
GIFARDECo
OUTCOMENew ESFR
concept
SP1Analytical assessment of
new safety measures for ESFR
SP3. Management and interactions
WP1.3Measures to prevent
sodium boilingKIT
WP1.4Measures to prevent
severe accidentsHZDR
WP1.5Measures to mitigate
severe accidentsKIT
SP2R&D to support
SFR safety enhancement
WP2.2New experiments
for safetyCEA
WP2.3European sodium facilities support
IPUL
WP2.4Instrumentation
for safetyHZDR
WP2.5New measurements
of fuel propertiesCEA
WP1.2Normal
operationPSI
WP1.1New safety measures
EDF
WP2.1Codes calibration
and validationIRSN
WP3.1Dissemination,education and
trainingCEA
WP3.2Project
managementPSI
1. Produce new experimental data in order to support calibration and validation of the computational tools for each defence-in-depth level.
2. Test and qualify new instrumentations in order to support their utilization in the reactor protection system.
3. Perform further calibration and validation of the computational tools for each defence-in-depth level in order to support safety assessments of Generation-IV SFRs, using the data produced in the project as well as selected legacy data.
4. Select, implement and assess new safety measures for the commercial-size ESFR, using the GIF methodologies, the FP7 CP-ESFR project legacy, the calibrated and validated codes and being in accordance with the update of the European and international safety frameworks taking into account the Fukushima accident.
5. Strengthen and link together new networks, in particular, the network of the European sodium facilities and the network of the European students working on the SFR technology.
Objectives
KASOLA
SPX KNS-37 SOLTEC CABRI SCARABEE
JOLO
LIVE MOCKA
CHUG
FAUST
NALA
FANAL
MOX fuel properties measurements Eddy-Current Flow Meter development
Starting ESFR design
The new project on Generation-IV Sodium Fast Reactor safety starts September 1, 2017 and ends on August 31, 2021. The project has received funding from the Euratom research and training programme 2014-2018 under grant agreement No 754501
Conclusions
Experience from EU projectsrelated to SFR safety
New SFR safety-related tests
Sodium facilities & instrumentation
Experience in SFR operation
Past SFR safety related tests
Experience in SFR
licensing
SFR safety-related education
ARDECo
SFR fuel measurements
