the progress of alisa project: access to large ... - the progress... · large infrastructures for...

May16-18, 2017

Warsaw, Poland

8TH CONFERENCE

ON SEVERE ACCIDENT

RESEARCH

ERMSAR 2017

The Progress of ALISA Project: Access to

Large Infrastructures for Severe Accidents

in Europe and in China

X. Gaus-Liu, A. Miassoedov, C. Journeau, Y. Liao,

N. Cassiaut-Louis

ERMSAR 2017, Warsaw, May 16-18, 2017

Overview of ALISA Project

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The project provides mutual access to large research infrastructures for European organizations and Chinese

partners: EU organizations have the access to Chinese facilities, and Vice Versa.

Project was started in July 2014 and the duration is 4 years.

There are two EU partners (KIT and CEA) and six Chinese partners (CNPRI, XJTU, SJTU, SNPSDC, CityU

HongKong, NPIC). NPIC is a new Chinese partner since Nov. 2016.

There are two financially independent projects: a Chinese project funds the experiments in China for EU

users, while EURATOM FP7 ALISA project funds the experiments in Europe for Chinese users. KIT is the

coordinator of EU project, while CNPRI is the coordinator of the Chinese project.

There are two work packages:

WP1: Experimental activities on Severe Accident Management (SAM)

WP2: Portal to Access to Large and Unique Infrastructures (PALI)

Two calls for proposal have been undertaken on Chinese and European facilities.


Selected Proposals on European Facilities

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Facility Phenomena User Status

QUENCH (KIT) In-vessel early core

degradation and

hydrogen take-up

XJTU, SNPTC Planed in

June 2017

LIVE (KIT) In-vessel melt behavior CNPRI Planed in

June 2017

HYKA (KIT) Hydrogen behavior in

containment

SJTU Performed in July 2016

DISCO (KIT) Containment direct

heating, Ex-vessel FCI

SNPTC In preparation

KROTOS (CEA) Medium scale FCI HKCU Performed in Nov. 2016

VITI (CEA) Thermo-physical

properties or

thermochemistry tests

CNPRI 2017 and 2018


Proposals on Chinese Facilities

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Facility Phenomena User Status

IVR-2D

(CNPRI)

Prototypical scale in-vessel melt retention

with external cooling

KIT Planed in late 2017

IVR-3D

(CNPRI)

1:5 scale IVR with external cooling CEA Planed in 2018

COPRA

(XJTU)

Prototypical scale in-vessel melt behavior KIT +EDF &

Partners

2017

HYMIT

(SJTU)

Mid-scale hydrogen behavior in

containment

JSI and partners Performed in

Oct. 2016

WAFT (SJTU) Containment water film passive cooling GRS In preparation

MCTHBF

(NPIC)

Containment H2 behavior JSI and partners In preparation


QUENCH test- AP1000 bundle design with peroxidation and air ingress

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20 heated rods, M5 cladding, ZrO2 pellet

2 unheated rods, M5 cladding, ZrO2 pellet

2 absorber bars, steel cladding

A similar test as QUENCH-16

pressurised, unheated

absorber rod

Preparation Heat-up to peak cladding temperature Tpct = 873 K

Phase I Stabilization at 873 K; facility checks

Phase II Heat-up to 1300 K during 2300 s

Phase III Pre-oxidation with superheated steam and argon during 4000 s, temperatures

increase from 1300 K to 1430 K. Reached ZrO2 thickness: 135 µm.

Phase IV Intermediate cooling from 1430 K to 1000 K during 1000 s in the same flow of steam

and argon.

Phase V

Air ingress and transient heat-up from 1000 K to 1873 K with heating rate of 0.2 K/s in a flow of 0.2 g/s of air and of 1 g/s of

argon for 4040 s. Total oxygen consumption during 835 s before end of this phase. For ALISA should be Tmax ≤ 1773 K to avoid

escalation during next phase.

Phase VI Quenching of the bundle by a flow of 50 g/s of water. Temperature escalation to 2420 K with intensive melt formation and

hydrogen release (128 g). The melt formation should be avoid in the test.


LIVE test- melt behaviour in lower head under different top boundary conditions

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Eutectic nitrate salt as simulant material

Two power levels for each upper boundary conditions

Pool height 410 mm

External cooling during whole test period

top cooling lid

Phase I top insulation with melt free surface

Phase II air-cooled lid

Phase III water cooled lid with crust formation

Answer the question of the influence of top boundary condition on

general Nuup and Nudn

heat flux distribution along vessel wall

convection pattern in the pool and melt temperature

provide data for the IVR external cooling strategy

Water/air


DISCO test- DCH and Ex-vessel FCI of AP1000 reactor type

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1:18 linear scaled containment

Reactor cooling system: 0.08 m³

Breach diameter: 60 mm

Simulant melt: iron oxide-alumina thermite

Initial H2 concentration up to 6%

New vessel including mounting parts

Simulating AP1000 reactor melt ejection in the water-filled

containment pit

Pressurization of the pit and containment during the mixing

Debris bed characteristics

Melt and water dispersion out of the pit

Impact of water on DCH: Oxidation of the iron compared with cases

without water

Hydrogen production and potential impact of water for combustion

Data for CosMetric code validation


HYKA-A2 test: Impact of H2 mixture nonuniformity and ignition position

8

Main goals:

The effect of mixture nonuniformity and ignition position on flame propagation

regimes and maximum combustion pressure in comparison with uniform mixture of

the same amount of hydrogen;

Ignition/extinction phenomena in presence of steam and/or water mixture

HYKA-A2 (V=220 m3)

Measurements: temperature, pressure, acoustic and optical observation using Method (BOS)

Performed test series

“Cold” (without combustion) testing of spray structure;

Flame propagation experiments for center ignition point with uniform hydrogen

concentration of 6%, 6.5%, and then 7%;

Flame propagation experiments with center ignition for three different vertical hydrogen

concentration gradients of 14%0%, 12%2% and 10%4%, that the hydrogen amounts

are equal to 7% of average concentration;

One test with upper ignition point and vertical hydrogen concentration gradient of

14%0%;

Two tests studying the effect of water stray on flame propagation with center ignition point

and vertical hydrogen concentration gradient of 14%0%.


KROTOS test- the effect of water pool depth on FCI

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Melting of 3.5 kg sample in 2700°C;

2nd experiment attempt was

successfully performed in Nov. 2016.

Load

composition

80 w% UO2, 20 w%

ZrO2

Load mass 3.5 kg

Load

temperature 2690 °C

Free fall in gas 492 mm

Pressure 2.1 Bar

Water level 645 mm

Water

temperature 60°C

water subcooling 67°C

Selection of smallest water depth:

0.645 m, comparing other tests with

the highest depth of 1.2 m

Pool depth ~ X-ray visualization field


VITI tests- 3 samples for in-vessel and ex-vessel corium scenarios

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Levitated droplet measurement

Droplet volume Density

Droplet shape Surface Tension

Droplet deformation Viscosity

composition, wt. % test phases

1 80% UO2, 20% ZrO2 (corresponding to in-vessel retention

scenarios and KROTOS ALISA condition)

• VITI-Levitation

2 46.1%UO2, 15.2%ZrO2, 19.1% SiO2, 5.1% CaO, 0.1%

MgO,1.8% Al2O3, 3.3% Fe2O3, 7.1% FeO, 2.2% Cr2O3

(corresponding to LBLOCA ex-vessel retention scenarios)

• Fabrication

• VITI-Levitation

3 33.9% UO2, 11.3% ZrO2, 29.6% SiO2, 6.7% CaO, 0.2% MgO,

2.4% Al2O3, 0.7% Fe2O3, 8.7% FeO, 6.5% Cr2O3

(corresponding to LOOP ex-vessel retention scenarios)

• Fabrication

• VITI-Levitation


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A full scale in-vessel melt external cooling facility

CHF and thermal-hydraulic tests for CPR1000, HPR1000 reactors

IVR 2D components: test section, riser channel, upper coolant tank,

downcomer channel, bottom feed water tank

Max heat flux: 2.4 MW/m2

Height of circulation loop: 8 m

Number of heater rods: 600 pcs

Independent heating zones：24

The proposed test investigates the influence of the penetrations

through the RPV lower plenum on the natural convection and

CHF.

Two heat flux distribution profiles are defined to simulate the

homogenous and stratified melt scenarios.

IVR2D test proposed by KIT


IVR3D test proposed by CEA/EDF/IRSN

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3D 1:5 scaled vessel external cooling facility

Studying 3D natural recirculation thermal-hydraulics, 3D CHF

distribution, CHF at bottom-most of reactor vessel

IVR3D components: lower head test section, insulation reflector,

cavity, recirculation loop

Test vessel inner diameter: 0.92 m, height: 1.68 m, height of whole

facility: 2.8 m

Max. heat flux: 1.8 MW/m², steel outer surface

Heater rods: ~1800 pcs

Thermal couples: ~250 pcs

Recirculation: natural or forced

The test investigates the influence of non-symmetrical

top conditions due to venting and non-symmetrical gap

around the RPV on the CHF

The experiment is planned in middle 2018.


COPRA test proposed jointly by EDF/CEA/IRSN and by KIT

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Top cooling

First melt pouring Second melt pouring Final power

plateau

(Tmax) Pool height Power input

(Tmax) Pool height

Power input

(Tmax)

Test 1 No 1.33 m 11 kW

(351.4 °C) 1.90 m

15 kW

(347.7 °C)

11 kW

(334.3 °C)

Test 2 Yes - - 1.90 m 28 kW

(334.2 °C)

21 kW

(324.3 °C)

Transient melt behavior after the initiation of external cooling

Scaling effect and influence of geometry on melt heat transfer in comparison

with LIVE3D and LIVE2D

Full scale 2D facility for melt behavior in PWR lower head

¼ circular pool, radius 2.2m, width:0.2m

ACP1000, Ra´=1016

Simulant: water, non-eutectic and eutectic nitrate salt

Heating: 20 heating rods (10 heating zones)

Upper boundary: insulated or cooling

External boundary: insulated or water cooling


HYMIT test proposed by JSI/PSF/NRG/KIT

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An experiment on hydrogen deflagration with upward flame propagation

in a homogeneous air-steam-hydrogen atmosphere

Answer the influence of scaling from small to large volumes on the

characteristics of hydrogen deflagration by comparing similar tests in

THAI (60m³) and in HYKA A2(220m³)

Proposed Executed 2016/10/17

Test type H2-Steam-Air Ignition H2-Steam-Air Ignition

H2 volume ratio 10%-12% 13.70%

Steam volume ratio 20%-25% 23.50%

A medium-scale facility designated for investigations of

hydrogen recombination and combustion behavior

Cylinder vessel with diameter of 2 m; height of 4 m and

volume of 12 m³


WAFT test proposed by GRS

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Studying Passive Containment Cooling System (PCCS)

of GEN-III plants.

Stainless plate with length of 5 m and width of 1.2 m

Uniform film distribution from box above the plate with

flow rate of 0.01-0.83 kg/(m·s)

Oil-heated plate with heat flux of 50-100 kW/m²

Uprising air velocity 0-12 m/s

Air temperature till 80 °C

Analyze the formation of rivulets at different angles and

water flow rates;

Validate the rivulet model describing the dry/wet surface

fraction in COCOSYS code;

Two tests are foreseen with the variation of

water flow

air flow

heating rate of steel plate

Measurements:

visualization of rivulets,

film temperature and film thickness


MCTHBF test proposed by JSI

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Midsize Hydrogen Mitigation Test Facility

Cylinder diameter 2.8 m, height 5 m, volume: 21 m³

H2 concentration: 0-35 vol%; steam concentration:

0-40 vol.%

Measurements: gas content, temperature and

pressure, and speed of flame

water

tank

water tank

hydrogen

supply system

heater

pump

air supply system

vaccum system

steam generator

MCTHBF test investigates the dilution of high hydrogen

concentration in the upper part of the vessel with a low-

momentum vertical steam jet located at the lower part (15

g/s, ambient temperature).

Helium simulates H2, and air simulates the steam jet.

Scaling from small to large volume for the validation of

lumped-parameter and Computational Fluid Dynamics

codes.


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Thank you for your attention

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