The CABRI reactor and the CIP Program - Idaho … Safety Presentations...The CABRI reactor and the...

The CABRI reactor and the CIP Program

GAIN Fuel Safety Workshop

1-4 May 2017Idaho Falls

Marc PETIT

IRSN/PSN-RES/SEREX

Once upon a time …

Mid 1962 1963GAIN Fuel Safety Workshop, May 2017, Idaho Falls 2

1963

1977-78

20012001-2002

2003

Sodium loop implementationNew core (UO2 rods)

Cabri first neutron early 64

SFR results still used today for the

ASTRID project

Same core reload in 2014

In parallel, tests in the sodium loop on fuel from

EDF PWRs (financial support from EDF and NRC) : first 2

CIP tests in 2001-2002

PWR test results used as reference for modifications in the regulations

International consensus on the need for tests in PWR representative conditions-> Pressurized Water Loop

CIP partners sign the umbrella agreement on 4

February

Tests dedicatedto research

reactors

Tests dedicated to sodium fast reactors

(Phénix Superphénix)

CABRI refurbishment and PWL implementation

GAIN Fuel Safety Workshop, May 2017, Idaho Falls 3

▌CABRI REP-Na program performed during the 1992-2002 period▌In reactor irradiation severely degrades the capacity of fuel rods to sustain ReactivityInitiated Accidents▌Beyond an external corrosion layer thickness of 80 microns, cladding integrity for Zr4(material used historically for PWRs) can’t be guaranteed

▌At the international level, results from CABRI REP-Na induced and provided inputto considerations on the necessity to revisit safety criteria established on lightly

irradiated fuels

▌In France, pending the complete deployment of cladding materials with improvedperformance, IRSN recommended to limit the operating conditions for Zr4containing cores in order to mitigate the risk

CABRI REP-Na 8

Clad

Fuel

Highly corroded cladding with spallation

Oxide thickness

80 µm 108 µm

No spalling Possible spalling Operating restrictions

Unauthorized Reactor shutdown

0 µm


▌CABRI is owned and operated by

• A decree gives priority to IRSN in order to use the reactor for its research programs on

fuel safety

• Refurbishment and operation of the reactor are 100 % sponsored by IRSN, CEA

remaining the owner

• Experimental program is directed by IRSN that also make use of its own experimental

devices

Cabri perfectly mimics Pressurized Water Reactor conditions thanks to

its Water Loop : 155 bars and 280°C flowing water

IRSN operates its specific instrumentation (Hodoscope, IRIS, …)

installed in CABRI

The reactor design allows performing rapid power transients


CABRI the movie


Modification and refurbishment of the CABRI Facility

Seismic reinforcement and replacement of the core

envelop

Design, manufacturing and implementation of the new

experimental loop

Design and production of a new handling and transportation cask

Inspection and reparation of the primary circuit

Refurbishment of the ventilation system

Design and implementation of a new waste management system

Seismic reinforcement of the building


Reactor building overview

Primary circuit

Travelling crane beam examination and reparation + seismic reinforcement

Reactor building overviewLifting trolley withdrawal

South wall reinforcement

Handling cask on its truck

Fuel rod examination

Glove box and biological shield before renovation

Glove box and biological shield after renovation

He Valves renovation

Regulatory examination glove box


Test device drawing (1/2)

Lower part: PW inlet and upstream instrumentation

Core zone: fuel test rodTest rod: 560mm

Upstream instrumentation: flow rate, pressure, temperature, microphone

Pressurised water inlet

Flange for introduction of the fuel test rod

Zy4 structures: neutronic transparencySS/Zy4 junctions

• Outer diameter : Ø72 à 140mm

• Length : 5m

• Weight : 140kg

• Main materials : SS and Zircaloy


Upper Part: PW outlet and downstream instrumentation

Head of the test device

Pressurised water outlet

Downstream Instrumentation : flow-rate, pressure sensor, temperature, microphone, axial expansion

Cabri WL closure and instrumentation

Test device drawing (2/2)


Upper part

Lower part

Core part(Spacer system)

Thermocouple

Thermocouple

Pressure sensor

Microphone Flow meter

Boiling onset

Rod axial elongation sensorThermocouple

Leak detector

Test device instrumentation


IRIS examination facility

Groundlevel

-5m

–8m

–11m

Examination bench located

inside the reactor hall

Reactor hall


What for ? Non Destructive Examination

▌X-ray radiography(contrast image – qualitative)

S c a n n i n g C I P 0 2 a p r è s e s s a i

0 . 0 E + 0 0

5 . 0 E + 0 2

1 . 0 E + 0 3

1 . 5 E + 0 3

2 . 0 E + 0 3

2 . 5 E + 0 3

3 . 0 E + 0 3

3 . 5 E + 0 3

4 . 0 E + 0 3

4 . 5 E + 0 3

5 . 0 E + 0 3

- 7 2 0 0- 7 1 0 0- 7 0 0 0- 6 9 0 0- 6 8 0 0- 6 7 0 0- 6 6 0 0- 6 5 0 0

C S - 1 3 7E U - 1 5 4 x 1 0

▌Gamma-scanning(quantitative -spectrometry)

▌X-ray transmission tomography(density map – quantitative)

Pre- and post-test:


Examination bench

▌Concrete shielding reinforced

▌Motorized lift (translation and rotation)reinforced, aligned

▌Airtight sheath new

▌Control & command (automaton, supervision & acquisition systems) new


X-ray imaging

Ground level: power electronics, modulator, HF wave generator

-6 m : accelerating sectionX-ray emission point

waveguide

X-ray generator:• Linear electron

accelerator• 8MeV max energy• 11Gy/min at 1m• spot size <1mm

X-ray digital camera

New Acquisition system

Optical alignment

Refurbished & requalified


-spectrometry

-5m level : gamma acquisition station

upgraded shielding

New detector(HP-Ge crystal) &

cryostat

acquisition system &

control/command


X-ray radiography▌Dummy pellets

▌Calibration standards cone-shaped stairs (beam hardening correction) calibrated thin plates (resolution estimation)

9x9mm test pattern


X-ray transmission tomography▌Calibrated dummy pellets (holes, slits)


• On-line fuel motion detection (displacement, ejection, relocation)

• measurement of the test rod fissile length

• measurement of the driver core power profile

• measurement of the pulse width

306 counting tracks: • 51 rows x 3 columns collimator • 153 237Np Fission Chambers • 153 Proton Recoil counters • up to 1 ms acquisition rate

Collimator Detectors

Hodoscope System


Collimator Housed in a sheath connected to the core by a bellow

Length : 3 m Weight : 5300 kg Material : Steel Motorized in rotation and

verticality 51 rows x 3 columns Distance to core axis : 1m

Channel size : Front side : 7.5 x 15 mm Back side : 10 x 20 mm Field of view at core axis: 10.2 x 20.4 mm

Collimator


Detector Bank153 Fission Chambers (FC) (237Np coating, Argon gas, 700V) Low efficiency, low dead time, high saturation level power transient measurement

153 Proton Recoil Counters (PR) (CH4 ionization chambers, 2.6kV) Higher efficiency, higher dead time“low” power measurement (up to ~100 MW).


Commissioning TestsAfter the refurbishing phase, a complete set of commissioning tests, from the sensors to the reactor itself

ComponentsCircuits

Facility

ActuatorsSensorsPumpsValves,Cables…

Transient rodsPressurized Water LoopPrimary Cooling CircuitVenting circuits,Waste circuitsIRIS…

Reactor functioning:Low and High power steady-stateTransient tests (start-up)


Qualification of the Pressurized Water Loop

Operation of the Water Loop at nominal conditions validated:

Temperature (280°C)

Pressure (155 bar)

Flow Rate (1.5 m3.h-1)

Temp. gradient (3 °C.min-1)

Control and command systems operability

PWL elongation criterion met

Primary WL Pump WL internals Heat Exchanger


Qualification of the 3He transient rod system3He transient rod system qualification

Depressurization kinetics

Time control system for valves opening

Security systems validation (core protection role)

Simple Depressurization

Double Depressurization

He-3 TankHe-3 Valves


Steady-state power tests

100 kW 2 MW 7 MW 14 MW 23 MW

▌Low power (<100kW) neutronics core characterization

Control rod and transient rod efficiency Kinetic parameters verification Reactivity effects (experimental cell

configuration, core stacking effect, isothermal temperature coefficient…)

▌High power (<24 MW) qualification Thermal balance Power chambers calibration Gamma heating evaluation


Start-Up transient tests▌Qualification of the whole facility (transient

rods, primary circuit, water loop, experimental measurements, data acquisition…)

▌Verification of the absence of impact on the transient of the Water Loop conditions

▌Qualification of the reactivity injection system (reproducibility, settings, 3He purity…)

▌Linearity of the power chambers demonstrated at high power

▌Hodoscope operability

Examples of double dep. pulses

Examples of single dep. pulses


Assessment of the CABRI transient capabilities▌CABRI core safety and operational limits verification:

Max fuel temp <2810°C Max clad temp <1300°C Max clad circum. deformation <3,65% Core primary water inlet temp <45°C Experimental cell max design temp <400°C Test device pressure tube max design temp < 355°C

▌66 transients performed over a large range of the CABRI domain: Prompt and sub-prompt tests Max core energy deposit > 230MJ Pulse FWHM between 9 and 80ms Max core power reached >21GW Still some margins! Capabilities to reach the CIP objectives demonstrated:

30ms pulses, >150 cal/g deposited in the test rod (assumed coupling factor)

10ms pulses with high energy deposit


Experimental study of RIA at IRSN

1st phase: CABRI REP-Na programSodium loop, 12 testsPCMI phase, rod failure threshold and mechanism, fuel ejection1992-2002 with EDF cooperation + US-NRC support

2nd phase: CABRI International Program (CIP)Pressurized water loop, 12 tests: 2 in sodium (CIP0) + 10 in waterUnder the auspices of OECD


Current CIP program test matrix

N° Test Rod Objective In Na in NSRR

1 CIPQ MOX Zr4 47 GWd/t Loop qualification – Boiling crisis X

2 CIP3-1 UO2 Zirlo 75 GWd/t Post failure events X X

3 CIP1-2 UO2 M5 77 GWd/t UO2 - Boiling crisis X X

4 CIP4-1 MOX-E M5 65 GWd/t MOX - Boiling crisis X

5 CIP4-1 HP MOX-E M5 65 GWd/t Effect of filling pressure

90b vs 50b in other tests

5 CIP4-2 MOX-SBR Zr4 60 GWd/t Post failure events

7 CIP3-3 UO2 Opt. Zirlo New cladding material

8 X UO2 M-MDA SR New cladding material X

9 Y Intermediate burnup

10 Z Improved PCI performance

The CIP program test matrix takes into account the current understanding and addresses some of the gaps to be filled


The “new” CABRI Reactor

▌Pool Type Reactor Core Size: 65x65x80cm Power Max:

Steady State: 25MW Pulse: 25GW (10-80ms)

Forced convection Water Cooled

▌ Fuel Rods 1488 UO2 (6% enriched) Stainless Steel Cladding

▌Test device conditions Pressurized water circulation P = 155 bar, T = 280°C, v = 4m/s


CABRI Experimental key figures▌Test rods

UO2 BU up to 100GWj/t [U] up to 4,95% Max Einj (100GWj/t-4,95%)=110cal/g

▌CIP “test procedure” Remanufacturing and characterization of the rodlet then NDE at IRIS station Start up campaign (reactivity system), isothermal test and thermal balance

(coupling factor and hodoscope measurement) Hodoscope pre-test plateau, transient test then hodoscope post test plateau NDE at IRIS station, test device embedding (in case of clad failure) and transfer

to hot cells NDE (visual inspection, clad diameter, oxide thickness…) DE: puncturing, macrographies, EPMA, samples preparation…

MOX BU up to 75GWj/t [U+Pu] up to 7,5% Max Einj (75GWj/t-7,5%)=150cal/g

Pre-test

D-Day

Post test


Thank you for your attentionMerci pour votre attention


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