Modelling of the contamination transfer in nuclear reactors: The OSCAR code Applications to SFR and ITER

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fr 1 st IAEA Workshop on Challenges for Coolants

1 Modelling of the contamination transfer in nuclear reactors: The OSCAR code Applications to SFR and ITER F. Dacquait, J.B. Génin, L. Brissonneau CEA/DEN/Cadarache 1 st IAEA Workshop on Challenges for Coolants in Fast Neutron Spectrum Systems Vienna (Austria), 5-7 July 2017 PAGE 1

2 Outline Introduction OSCAR: the main specifications OSCAR-Fusion: Application to ITER OSCAR-Na: Application to SFR Conclusion 1st IAEA Workshop on Challenges for Coolants in Fast Neutron Spectrum Systems Vienna (Austria) 5-7 July 2017 PAGE 2

3 Introduction OSCAR: The main specifications OSCAR-Fusion: Application to ITER OSCAR-Na: Application to SFR Conclusion PAGE 3 JUIN 2015

Introduction - Principle and stakes Collective dose for operation and maintenance of PWRs Principle of contamination transfer in a nuclear cooling system ACP transfer Contamination Neutrons 5%

4 Introduction - Principle and stakes Collective dose for operation and maintenance of PWRs Principle of contamination transfer in a nuclear cooling system ACP transfer Contamination Neutrons 5% Activated Fission structures products 5% 5% Activated Corrosion Products (ACPs) 85% For ITER and SFR: mainly due to ACPs as well Under neutron flux Activation and release of ACPs CP transfer Out-of-flux Corrosion and release of CPs Industrial issues: Radioprotection: Reduction of Occupational Radiation Exposure (ORE) Environment: Minimization of release/waste Optimization of dismantling process Source term in case of accident/incident Availability: Optimization of reactor operation 1st IAEA Workshop on Challenges for Coolants in Fast Neutron Spectrum Systems Vienna (Austria) 5-7 July 2017 PAGE 4

Introduction - Scientific process at CEA Studies Predictions Valuations and solutions Radiotracers injection pots of CIRENE OSCAR code Development Validation

Solubility/Dissolution kinetics (SOZIE ) Transfer/Deposition (CIRENE) Study of phenomenology Data acquisition Modelling Validation Measurements in nuclear

5 Introduction - Scientific process at CEA Studies Predictions Valuations and solutions Radiotracers injection pots of CIRENE OSCAR code Development Validation Simulation PWR / NMP / JHR / ITER / SFR EMECC measurement Hot leg of a PWR Experiments in test loops Corrosion/Release (CORELE, autoclaves ) Solubility/Dissolution kinetics (SOZIE ) Transfer/Deposition (CIRENE) Study of phenomenology Data acquisition Modelling Validation Measurements in nuclear reactors EMECC campaigns (g surface activities) Filtrations / Samplings 1st IAEA Workshop on Challenges for Coolants in Fast Neutron Spectrum Systems Vienna (Austria) 5-7 July 2017 PAGE 5

6 Introduction OSCAR: The main specifications OSCAR-Fusion: Application to ITER OSCAR-Na: Application to SFR Conclusion PAGE 6 JUIN 2015

OSCAR: the main specifications Objective Simulation of contamination transfer in nuclear reactor systems during power operation and during cold shutdown (PWR: 20 350 C - reducing/oxidizing -

7 OSCAR: the main specifications Objective Simulation of contamination transfer in nuclear reactor systems during power operation and during cold shutdown (PWR: C - reducing/oxidizing - acid/alkaline) Calculation of masses/activities of CPs/ACPs/FPs/Actinides in solid/liquid/gaseous phases of nuclear circuits as a function of time (normal operation over several decades and transients over several minutes/hours) Development of a calculation code since 70 s: OSCAR (merge of former PACTOLE and PROFIP codes in 2008) Outil de Simulation de la ContAmination en Réacteur (tool of Simulation of ContAmination in Reactor) OSCAR originally developed for PWR in collaboration with EDF and AREVA NP Modular code (easy evolving tool) Validation based on a large OPEX unique in the world (~400 EMECC campaigns) Last version: OSCAR V1.3 released in 2014 Application to ITER: PACTOLE-ITER (1995) PACTITER (1998) OSCAR-Fusion (2016) Application to SFR: OSCAR-Na (2012) 1st IAEA Workshop on Challenges for Coolants in Fast Neutron Spectrum Systems Vienna (Austria) 5-7 July 2017 PAGE 7 SFR

OSCAR: the main specifications Modelling - Discretization Circuits discretized in control volumes according to: material geometry thermal-hydraulics neutronics operation Core Filters Ions Particles

8 OSCAR: the main specifications Modelling - Discretization Circuits discretized in control volumes according to: material geometry thermal-hydraulics neutronics operation Core Filters Ions Particles Deposit/Outer oxide Inner oxide Metal Up to 6 media in each control volume PWR HL/COL/CL : Hot/CrossOver/Cold Leg SG: Steam Generator CVCS: Chemical and Volume Control System 1st IAEA Workshop on Challenges for Coolants in Fast Neutron Spectrum Systems Vienna (Austria) 5-7 July 2017 PAGE 8

9 OSCAR: the main specifications Modelling - Isotopes and mass balance equations CPs/ACPs (OSCAR V1.3): 8 elements: Ni, Co, Fe, Mn, Cr, Zr, Ag, Zn 15 radioisotopes (short/long half-lifes) Unsteady mass balance equation for each isotope in each medium of each region: m t i Source J m Sink J m m i : mass of isotope i in a medium J m : mass flux between 2 media or 2 isotopes or 2 regions 1st IAEA Workshop on Challenges for Coolants in Fast Neutron Spectrum Systems Vienna (Austria) 5-7 July 2017 PAGE 9

Abrasion Activation Decay Formation Deposit/Outer oxide Formation Inner oxide Corrosion Metal Region k 1st

10 OSCAR: the main specifications Modelling - Transfer mechanisms of CPs Injection Convection Ions Dissolution Precipitation Release Filters Purification Precipitation Dissolution Particles Erosion Deposition Convection Abrasion Activation Decay Formation Deposit/Outer oxide Formation Inner oxide Corrosion Metal Region k 1st IAEA Workshop on Challenges for Coolants in Fast Neutron Spectrum Systems Vienna (Austria) 5-7 July 2017 PAGE 10

11 OSCAR: the main specifications Modelling - Corrosion-Release M Z+ : metal ion *M Z+ : radioactive metal ion M Z+ Release Outer oxide growth Inner oxide growth *M Z+ M Z+ M Z+ Ferrite + pure phase Chromite Corrosion Corrosion and release rates [kg s 1 ]: Corrosion Empirical laws (material, chemistry, temperature) User data (power law, logarithmic law, constant value per stage) J S m V Cor J Release S m V Rel 1st IAEA Workshop on Challenges for Coolants in Fast Neutron Spectrum Systems Vienna (Austria) 5-7 July 2017 PAGE 11

12 OSCAR: the main specifications Modelling - Dissolution/Precipitation Dissolution rate [kg s 1 ] J elt dissolution Sw 1 1 h V dissol ( C elt eq C elt ) S w : wetted surface [m²] h : mass transfer coefficient of ions in fluid [m.s -1 ] V dissol : dissolution surface reaction rate coefficient [m.s -1 ] elt : equilibrium concentration of element elt [kg.m -3 ] C eq C elt : bulk concentration of element elt [kg.m -3 ] Equilibrium concentrations and composition of ideal solid solution (mixed oxide and pure solid phases in excess): calculated by PHREEQCEA (OSCAR chemistry module) (version of PHREEQC code extended to 350 C) and its thermodynamic database developed by CEA Depend on chemical conditions (ph, redox), bulk/wall temperature and masses of each medium in each region 1st IAEA Workshop on Challenges for Coolants in Fast Neutron Spectrum Systems Vienna (Austria) 5-7 July 2017 PAGE 12

13 OSCAR: the main specifications Modelling - Erosion/Deposition Erosion rate [kg s 1 ] J E Y Erosion m erod E : erosion coefficient [s -1 ] (based on Cleaver & Yates model) Y : erosion resistance [-] E p K log rég Fluide m erod : mass of the deposit that can be eroded [kg] Deposition rate [kg s 1 ] J Deposition S w V deposition C part V deposition : deposition velocity [m.s -1 ] taken into account Brownian diffusion, inertial deposition (Beal model), sedimentation, thermophoresis and boiling deposition C part : particle concentration [kg.m -3 ] 1st IAEA Workshop on Challenges for Coolants in Fast Neutron Spectrum Systems Vienna (Austria) 5-7 July 2017 PAGE 13

14 Introduction OSCAR: The main specifications OSCAR-Fusion: Application to ITER OSCAR-Na: Application to SFR Conclusion PAGE 14 JUIN 2015

15 OSCAR-Fusion: Application to ITER ITER (fusion reactor) Tokamak Water Cooling System consists of 3 Primary Heat Transfer Systems (IBED, NBI, VV) Compared to LWRs: Similarities: Coolant: water Water characteristics (thermohydraulic and chemical) Materials: SS 316/304 Differences, mainly: CuCrZr alloy (Plasma Facing Components) Pulsed mode operation Neutron flux Typical ITER TCWS cooling loop (Gopalapillai et al., 2012) Cooling water chemistry specification for plasma operation (Gopalapillai et al., 2012) OSCAR can be used for ITER & DEMO with some minor adaptations 1st IAEA Workshop on Challenges for Coolants in Fast Neutron Spectrum Systems Vienna (Austria) 5-7 July 2017 PAGE 15

16 OSCAR-Fusion: Application to ITER OSCAR-Fusion: OSCAR Cu (thermodynamic data in PHREEQCEA and CuZrCr corrosion rate) Activation reaction rates (fast neutron flux) E.g. Simulation of the ITER DIV/LIM cooling loop using OSCAR-Fusion V1.3 CVCS HE DIV Circuit discretization (Di Pace, 2003): 71 control volumes 1st IAEA Workshop on Challenges for Coolants in Fast Neutron Spectrum Systems Vienna (Austria) 5-7 July 2017 PAGE 16

17 Temperature ( C) OSCAR-Fusion: Application to ITER E.g. Simulation using OSCAR-Fusion V1.3 (continued) Operating scenario (Di Pace, 2003) Total out-of-flux wall activity (Broutin, 2017) Baking Baking 150 Burn Burn Burn 100 Hot stby Dwell + Hot stby Hot stby Dwell + Hot stby 50 Cold stby Cold stby Time (days) Out-of-flux wall g activities due to: Generally 64 Cu during plasma burn phases 60 Co during the other phases 1st IAEA Workshop on Challenges for Coolants in Fast Neutron Spectrum Systems Vienna (Austria) 5-7 July 2017 PAGE 17

stand-by, baking and shutdown phases About 400,000 burn phases of 400 s over about 20 years

18 OSCAR-Fusion: Application to ITER Issues/R&D needs (discussion with L. Di Pace from ENEA): Simulation of pulsed mode (in progress): succession of burn, hot and cold stand-by, baking and shutdown phases About 400,000 burn phases of 400 s over about 20 years 1st IAEA Workshop on Challenges for Coolants in Fast Neutron Spectrum Systems Vienna (Austria) 5-7 July 2017 PAGE 18

19 OSCAR-Fusion: Application to ITER Issues/R&D needs (continued): Validation of OSCAR-Fusion against experiments in ITER/DEMO PHTS conditions Optimization of chemistry conditioning for each PHTS and each operating phase Corrosion rates of steels and Cu alloys (impact of Cu swirls?) in different conditions Impact of manufacturing process (surface finish) Cooling water chemistry specification for plasma operation (Gopalapillai et al., 2012) Corrosion at material junctions like CuCrZr and SS: impact on contamination? Effect of the magnetic field on the CP behaviour 1st IAEA Workshop on Challenges for Coolants in Fast Neutron Spectrum Systems Vienna (Austria) 5-7 July 2017 PAGE 19

20 Introduction OSCAR: The main specifications OSCAR-Fusion: Application to ITER OSCAR-Na: Application to SFR Conclusion PAGE 20 JUIN 2015

21 OSCAR-Na: Application to SFR SFR Sodium Fast Reactor Coolant: Sodium - Temperature up to 600 C Adaptation of OSCAR to SFR OSCAR-Na: Architecture of OSCAR specific corrosion-dissolution/precipitation model Convection Interface flux ION Sodium Convection 1) Release from activated cladding Corrosion of cladding steel 2) ACPs transported by Na METAL Control volume k 3) Out-of-flux contamination Precipitation on cold surfaces 1st IAEA Workshop on Challenges for Coolants in Fast Neutron Spectrum Systems Vienna (Austria) 5-7 July 2017 PAGE 21

22 OSCAR-Na: Application to SFR Corrosion-dissolution/precipitation model: (Polley & Skyrme, 1978) model Interface flux: C D x x 0 u C i k k a Ci C' Steel Sodium D k k a d C C' i eq : Chemical partition coefficient k Calculation: Numerical method for solving the equation diffusion Complete mass balance in the primary circuit Iterations convergence for each time step M.V. Polley and G. Skyrme, An analysis of radioactive corrosion product transfer in sodium loop systems, Journal of Nuclear Materials 75 (1978) st IAEA Workshop on Challenges for Coolants in Fast Neutron Spectrum Systems Vienna (Austria) 5-7 July 2017 PAGE 22

Fuel regions OSCAR-Na: Application to SFR E.g. Simulation of the PHENIX reactor using OSCAR-Na V1.

23 Fuel regions OSCAR-Na: Application to SFR E.g. Simulation of the PHENIX reactor using OSCAR-Na V core regions 10 IHX regions [O] = 1 ppm Purification : 0,14% primary flow Simulation covers 1750 days at nominal power Calculation time ~ 30 minutes 1st IAEA Workshop on Challenges for Coolants in Fast Neutron Spectrum Systems Vienna (Austria) 5-7 July 2017 PAGE 23

24 OSCAR-Na: Application to SFR E.g. Simulation of the PHENIX reactor using OSCAR-Na V1.3 (continued) The global amount of contamination and the contamination profiles on PHENIX IHX are correctly simulated using OSCAR-Na 1st IAEA Workshop on Challenges for Coolants in Fast Neutron Spectrum Systems Vienna (Austria) 5-7 July 2017 PAGE 24

25 OSCAR-Na: Application to SFR Issues/R&D needs: Data on oxide equilibrium concentrations (only pure element solubility in sodium are known) Data on diffusion coefficient in steel Particle behaviour Further OSCAR-Na validation work against OPEX on SFRs and experimental loops Modelling of contamination by fission products 1st IAEA Workshop on Challenges for Coolants in Fast Neutron Spectrum Systems Vienna (Austria) 5-7 July 2017 PAGE 25

26 Introduction OSCAR: The main specifications OSCAR-Fusion: Application to ITER OSCAR-Na: Application to SFR Conclusion PAGE 26 JUIN 2015

27 Conclusion - Graphview Application Fusion reactor cooling water system SFR primary system Main Radiation Effects 1. Formation of ACPs under neutron flux 2. Contamination of out-of-flux regions by ACPs Research Details OSCAR-Fusion: Cu alloy added OSCAR-Na: Specific dissolutionprecipitation model implemented Major Issues and Challenges Validation against experimental data (loop/reactor OPEX) Modelling of Contamination Transfer Achievement (ITER and SFR) Adaptation of OSCAR (modular code) to different types of coolant R&D Needs Fusion: Simulation of pulsed mode / Corrosion of Cu alloys (Cu swirls), steels / Optimization of water chemistry / Validation experiments / SFR: Oxide solubility / Diffusion coefficient in steel / Particle behaviour / Validation / F. Dacquait Modelling of the contamination transfer in nuclear reactors: The OSCAR code - Applications to SFR and ITER 1st IAEA Workshop on Challenges for Coolants in Fast Neutron Spectrum Systems Vienna (Austria) 5-7 July 2017 PAGE 27

Thank you for your attention PAGE 28 JUIN 2015 Commissariat à l énergie atomique et aux énergies alternatives Centre de Cadarache 13108 Saint-Paul lez Durance Cedex T. +33 (0)1 04 42 25 75 74 F.

28 Thank you for your attention PAGE 28 JUIN 2015 Commissariat à l énergie atomique et aux énergies alternatives Centre de Cadarache Saint-Paul lez Durance Cedex T. +33 (0) F. +33 (0) Etablissement public à caractère industriel et commercial RCS Paris B Direction de l Energie Nucléaire Département de Technologie Nucléaire Service de Mesures et modélisation des Transferts et des Accidents graves Laboratoire de Modélisation des interactions et Transferts en Réacteur

Sodium quality control in Sodium Fast Reactors. By Christian Latgé 1,

1 st International Topical Seminar Coolants and Innovative Reactor Technologies organized within the framework of CEA and JAEA Collaboration and GEDEPEON Sodium quality control in Sodium Fast Reactors