M. GIRARD – CEA / EFDA MEETING - CADARACHE, January th, 2005 Task TW4 – TSS - SEA 5.5 Validation of EU Safety Computer codes Validation of PACTITER - Feasibility study on ACP deposition experiments M. GIRARD CEA DTN/STRI - CADARACHE

M. GIRARD – CEA / EFDA MEETING - CADARACHE, January th, 2005 THE ITEM of the FEASIBILITY STUDY The Tokamak Cooling Water Systems (TCWS) have water cooled copper and stainless steel components activated corrosion products in the fluid and on the inner surfaces of the pipes The CIRENE loop is devoted to study PWR corrosion product deposition The PACTITER code requires experimental tests to be validated Simulation of TCWS tests in the CIRENE out-of-pile loop of the CEA - Cadarache ?

M. GIRARD – CEA / EFDA MEETING - CADARACHE, January th, 2005 THE ITEM of the FEASIBILITY STUDY  Thermal-hydraulic data  Chemistry of the coolant  Materials corrosion products (CP), ACP  Volumes and surfaces of the circuit CIRENE / TCWS TCWS : a new corrosion product to study, Cu

M. GIRARD – CEA / EFDA MEETING - CADARACHE, January th, 2005 THE CIRENE OUT OF PILE LOOP - CEA CADARACHE  Operating conditions Fluid temperature : from 60 °C to 345°C Pressure : from 20 to 150 bar (15 Mpa) Mass flow rate  6 m 3 /hr  Coolant chemistry Controled chemistry : additive concentrations, O 2 and H 2 contents Continuous injection of corrosion products (in soluble state or as particles ) and radioactive tracers (  emitters)  Transient and shutdown scenariis  Continuous in-line deposition measurements by g spectrometry Under thermal flux section Heat flux up to 85 W/cm 2 Fluid velocity : m/s devoted to study PWR corrosion product deposition

M. GIRARD – CEA / EFDA MEETING - CADARACHE, January th, 2005 CURRENT CIRENE LOOP OUTLINES

M. GIRARD – CEA / EFDA MEETING - CADARACHE, January th, 2005 RCS (main pipes) 316 L stainless steel m² Under thermal flux section (16 % of the total area) Zry 4 claddings 316 L Stainless steel square tube outlet primary heat exchanger S.G. tubes Ni based alloy Ion injection device : ionic PC source term Fe, Ni ACP source term : radioactive ion injection device Fe, Ni, (Co, Cr) Out-of-flux section (84% of the total area) PWR CIRENE area ratios Ni based alloys : 20 % ( 0.81 m 2 ) Stainless steel : 70 % (2.67 m 2 ) Zircaloy : 10 % (0.40 m 2 ) CIRENE loop areas adapted to PWR tests

M. GIRARD – CEA / EFDA MEETING - CADARACHE, January th, 2005 ITER OPERATING PERIODS DIV/LIM zone TH data Operating periods (assumed scenario) Cold standbyBakingHot standbyPlasma burnDwell Under flux zone (S. steel and Cu) Fluid T.50°C240°C100°C °C °C Velocity (m/s) (S.s) (Cu) (S.s) (Cu) (S.s) (Cu) (S.s) (Cu) (S.s) (Cu) Out-of-flux zone (S. steel) Fluid T.50°C240°C100°C °C100°C Velocity

M. GIRARD – CEA / EFDA MEETING - CADARACHE, January th, 2005 CIRENE outlines for PWR testsoutlines for DIV/LIM tests Under flux sectionZy4 claddings area / heating rods Thermal flux section  T ~ °C and v ~ m/s Stainless steel and CuCrZr alloy area Thermal flux section design to define for  T ~ 50°C and velocity from 1 to 11 m/s Out-of-flux sectionStainless steel pipesidem Heat exchangerNi based alloy, S.G tubes  T ~ 30°C Stainless steel design to define for  T > 50°C and velocity from 0.01 to 1 m/s Circulation pumpFixed flow rateVariable flow rate Implemented devicesIon and radionuclide injections Adapted to PWR corrosion products Idem Adapted to TWCS corrosion products Comparison between PWR and DIV/LIM loop outlines

M. GIRARD – CEA / EFDA MEETING - CADARACHE, January th, 2005 Stainless steel (80%) CuCrZr alloy (20%) Heat exchanger Stainless steel area Under neutronic flux section (22 % total area) Auxiliary heater Out-of-flux section (78 % total area) Circulation pump (variable flow rate)  T ~ 50°C fluid velocity up to 11 m/s Main pipes Stainless steel alloys max.T = 240 °C Outlines required for an ITER TCWS loop must be as representative as possible of TCWS situations must reproduce ITER-like CRUD deposits on piping must be as representative as possible of TCWS situations must reproduce ITER-like CRUD deposits on piping  must be as representative as possible of TCWS situations  must reproduce ITER-like CRUD deposits on piping

M. GIRARD – CEA / EFDA MEETING - CADARACHE, January th, 2005 REQUIRED CHARACTERIZATIONS FOR ITER TWCS TESTS  in operation Chemical analyses of Cu, Fe, Ni, Co, Cr...in the coolant : concentrations in soluble ( ~ kg/kg H2O ) and particulate states In - line  spectrometry analyses in the under and out-of-flux sections : measurements of the injected radionuclides as 58 Co, 59 Fe and 51 Cr 64 Cu (  ) has a short radioactive half-time ( T 1/2 : 12 hours ) in - situ (  ) measurements through neutron bombardment ? correlation between a well-known gamma emitter ?  after shutdown Idem above (chemical analyses of the coolant and  spectrometry measurements) Scrapings undertaken on the sections in study Scraping analyses through chemical and spectrometry investigations

M. GIRARD – CEA / EFDA MEETING - CADARACHE, January th, 2005 In-situ 64 Cu (  ) local measurements, through neutron bombardment  spectrometer Generator 30° collimator neutronic absorber Gamma-ray Spectrometer thermal neutron source thermal neutron + 63 Cu 64 Cu (  ) CuCrZr area Required faisibility and experimental studies

M. GIRARD – CEA / EFDA MEETING - CADARACHE, January th, 2005 CIRENE OUTCOMES Required modificationsOptionsComments Materials under flux section external injections of CP (dedicated devices) lack of representativity and restricted v. Thermal - hydraulic circulation pump (variable velocities) current circulation pump restricted simulation with 2 < v < 4 m/s CP deposit measurements in - line (  ) measurements of 59 Fe, 58 Co, 51 Cr 64 Cu (  ) by neutron bombardement Chemical analyses of residual deposits no monitoring of the Cu element in the deposits heat - exchanger no alternatived (  T  50°C) solution

M. GIRARD – CEA / EFDA MEETING - CADARACHE, January th, 2005 OTHERS POTENTIAL SOLUTIONS for ACP TRANSPORT STUDIES  In-line analyses of Cu deposits Transfer correlation between a well-known gamma emitter and Cu ? Experimental validation of such correlation could be undertaken in the CORELE loop (LTCD)  Cu equilibrium solubilities in the overall spectrum of T°C and coolant conditionning of a TWCS loop Complementary tests could be carried out in s. steel autoclaves with recirculation (LTCD)  Deposition and release studies Towards a dedicated CORELE ITER test facility : needs some modifications to be devoted to ITER deposit studies

M. GIRARD – CEA / EFDA MEETING - CADARACHE, January th, 2005 CONCLUSIONS The CIRENE facility  required some modifications to be representative of an TCWS loop, with designs to define and relevant budgets to evaluate ;  unavailable in-line measurements of copper deposits further investigations on   Cu (  ) through Neutron bombardment and on a correlation between Cu and a well-known gamma emitter (tests proposed in the CORELE loop)  the use of external injection devices required data related to CuCrZr* and stainless steel release rates in the overall spectrum of ITER operating conditions (T-H and chemical conditions) Complementary studies on TCWS Corrosion Product deposits  CuCrZr release rates can be studied in the updated CORELE loop  Modifications of the CORELE loop to be adapted to ITER ACP deposit studies (including Cu element) ?

M. GIRARD – CEA / EFDA MEETING - CADARACHE, January th, 2005