Post on 18-Dec-2015
M. GIRARD – CEA / EFDA MEETING - CADARACHE, January 25-26 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 25-26 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 25-26 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 25-26 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 m3/hr
Coolant chemistry
Controled chemistry : additive concentrations, O2 and H2 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/cm2
Fluid velocity : 3.5 - 4 m/s
devoted to study PWR corrosion product deposition
M. GIRARD – CEA / EFDA MEETING - CADARACHE, January 25-26 th, 2005
Thermal pressurizermax. P = 15 MPa (155 bar)
Circulation pump max. Q = 6 m3/h fixed flow rate
CVCSAuxiliary heater max. W = 37 kW
H2O
Li, B
1 - Ion injectiondevice
Makeuptank (200 l)
RCS
Primary heat exchangerC
ore
sect
ion
max.T = 342 °C
max. W 4 x 46 kW
O2 H2 pH eRedoxT
T
T
T2 - Radioactive knit-meshes
3 - Radioactive
ion injection device
Additional vessel
Sampling
(V 10 valve)
CURRENT CIRENE LOOP OUTLINES
M. GIRARD – CEA / EFDA MEETING - CADARACHE, January 25-26 th, 2005
RCS (main pipes)316 L stainless steel - 2.3 m²
Under thermal flux section
(16 % of the total area)
Zry 4 claddings
316 L Stainless steel square tube
outlet primary heat exchangerS.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 m2)
Stainless steel : 70 % (2.67 m2)
Zircaloy : 10 % (0.40 m2)
CIRENE loop areas adapted to PWR tests
M. GIRARD – CEA / EFDA MEETING - CADARACHE, January 25-26 th, 2005
ITER OPERATING PERIODS
DIV/LIM zone
TH data
Operating periods (assumed scenario)
Cold standby Baking Hot standby Plasma burn Dwell
Under flux zone
(S. steel and Cu)
Fluid T. 50°C 240°C 100°C 100 - 152°C 100 - 106°C
Velocity(m/s)
0.02 - 3.2 (S.s)
0.8 - 1.1 (Cu)
0.02 - 4 (S.s)
1 - 1.3 (Cu)
0.02 - 3.8 (S.s)
0.8 - 1.1 (Cu)
0.7 - 6.7 (S.s)
8.5 - 11.7 (Cu)
1.4 - 7.2 (S.s)
8.4 - 11.4 (Cu)
Out-of-flux zone
(S. steel)
Fluid T. 50°C 240°C 100°C 150 - 100°C 100°C
Velocity 0.3 - 0.5 0.3 - 0.6 0.3 - 0.5 3 - 5 2.8 - 5.5
M. GIRARD – CEA / EFDA MEETING - CADARACHE, January 25-26 th, 2005
CIRENE outlines for PWR tests outlines for DIV/LIM tests
Under flux section Zy4 claddings area / heating rods
Thermal flux section
T ~ 30 - 50°C and v ~ 3 - 4 m/s
Stainless steel and CuCrZr alloy area
Thermal flux section
design to define forT ~ 50°C and velocity from 1 to 11 m/s
Out-of-flux section Stainless steel pipes idem
Heat exchanger Ni 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 pump Fixed flow rate Variable flow rate
Implemented devices Ion 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 25-26 th, 2005
Stainless steel (80%)
CuCrZr alloy (20%)
Heat exchanger Stainless steel area
Under neutronicflux 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
M. GIRARD – CEA / EFDA MEETING - CADARACHE, January 25-26 th, 2005
REQUIRED CHARACTERIZATIONS FOR ITER TWCS TESTS
in operation
Chemical analyses of Cu, Fe, Ni, Co, Cr...in the coolant : concentrations in
soluble ( ~ 10-9 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 25-26 th, 2005
In-situ 64 Cu ( ) local measurements, through neutron bombardment
spectrometer
Generator
30°
collimator
neutronicabsorber
Gamma-raySpectrometer
thermal neutron source
thermal neutron + 63 Cu 64 Cu ()
CuCrZr area
Required faisibility and
experimental studies
M. GIRARD – CEA / EFDA MEETING - CADARACHE, January 25-26 th, 2005
CIRENE OUTCOMES
Required modifications Options Comments
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 59Fe, 58Co, 51 Cr
64Cu () 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 25-26 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 25-26 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 25-26 th, 2005