M. GIRARD – CEA / EFDA MEETING - CADARACHE, January 25-26 th, 2005 Task TW4 – TSS - SEA 5.5...

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


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 ?


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


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


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


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


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


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


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


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


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


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


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


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 Task TW4 – TSS - SEA 5.5...

Documents

Transcript of M. GIRARD – CEA / EFDA MEETING - CADARACHE, January 25-26 th, 2005 Task TW4 – TSS - SEA 5.5...