advanced technology experiment sodium facility (athena

Japan Atomic Energy Agency

Advanced Technology Experiment

Sodium Facility (AtheNa)

and related R&D activities

10–12 June 2013

Satoshi FUTAGAMI

Japan Atomic Energy Agency (JAEA)

Technical Meeting on

Existing and Proposed Experimental

Facilities for

Fast Neutron Systems


CONTENTS

1. Introduction

2. AtheNa experimental plan

3. AtheNa facility

4. Current status and SA GIF collaboration

5. Conclusions

1


1. Introduction

2


Experimental needs

① Innovative Technology for JSFR• Integrated IHX-Pump component

• Straight double-wall tube large SG

② Fukushima 1 NPP accident • Long term Station Blackout (SBO)

→Natural Circulation Decay Heat Removal

• Decay Heat Removal System for Severe Accident

→prevention and mitigation measures

Needs of Sodium Experiment• Large-size component

→Confirmation of functions and integrity of sodium components

• Stable and safety operation in sodium

→System demonstration of innovative and new design concept

3


Outline of Sodium tests

4

• Component development test– SG test：

• To verify heat transfer rate of 29m length tube bundle

• To verify flow stability of boiling multi-channels

– Pump test

• To verify long axle stability

• System and Component Demonstration test – Partially Integrated System demonstration test or

Whole Integrated system demonstration test

• To demonstrate cooling components and system

• (Whole integrated system demo. Test) + to demonstrate NCDHR

– Integrated pump-IHX test

• To demonstrate Integrated pump-IHX component

• Equipments demonstration in sodium – ISI devices

– Fuel handling machine

– Rotating plug

– Control rod drive mechanism , etc

For

Demonstration reactor

component design

+ Experiments for Severe

Accident counter measures


2. AtheNa experimental plan

5

Japan Atomic Energy Agencywater

Tube

bundle

steam

Na

Tube

sheet

Na

CSEJ

⑤⑤⑤⑤D/W tube, tube sheet, CSEJ structure

• To identify developed structures

①①①①Flow stability of steam flow

• Parallel channel flow stability of long boiling 2-

phase flow

⑥⑥⑥⑥Uniform flow distribution

• Uniform Na flow distribution for less

temperature distribution in tube bundle

⑧⑧⑧⑧ISI & R

• To identify ISI & R methods

②②②②Heat transfer capacity

• Heat transfer correlation of long tube

• The countermeasures for stable steam flow (long tube)

should be verified by sodium experiments.

• Heat transfer correlation should be obtain from sodium

experiments.

⑦⑦⑦⑦Na-water reaction evaluation

• Accurate evaluation on water leakage event

• Water test for optimizing inlet plenum and baffle plate

is planed

• Temperature distribution should be verified by sodium

experiments

• Experimental studies are planed in existing facilities

(SWAT-1 and SWAT-3)

• Demonstration in sodium is needed

③③③③High Cr steel thin wall tube integrity

• To identify high Cr thin tube integrity

④④④④Tube sheet joint structure integrity

• To identify tube sheet welding joint integrity

• Innovative high Cr steel structures should be identified by

sodium experiments step by step.– Thin tube

– Tube-sheet joint

– Double wall tube

– Very thick tube sheet

– CSEJ

Component development test


Demonstration test

Demonstration test

Demonstration test

Sodium Experiment items : Straight double-wall tube SG

6


Scaling of test section: Straight double-wall tube SG

Component development test (ca. 10MW thermal output)

� To simulate thermo-hydraulics

� Heat transfer distribution at tube wall

� Multi-channel flow stability of 2 phase

flow without inlet orifice

� To simulate sodium flow field

� Edge effect

� Single tube plugged condition

System & component demonstration test (ca. 50MW thermal output)

� To demonstrate innovative structures

� High Cr steel applied double-wall tube,

tube-sheet joint, CSEJ

� ISI & R

� To demonstrate integrity

� Structural integrity with multi-plugged tubes

1/1 tubes（single-wall tube）

Min. 4 rows tube bundle

1/1 tubes (double-wall)

Min. 8 rows tube bundle

7


IHX

Pump

Motor

Primary

Na

Primary Na

Secondary

Na

Secondary

Na

①①①①Stability of long axle• Rotating stability of long axle with

flexible structure

②②②②IHX tube fretting• IHX tube fretting by vibration from the

pump

④④④④Upper plenum form

•Manufacturing procedure

•Uniform flow distribution to tubes

• 1/4-scaled water test (pump) and

1/1-scaled bearing test will be

continued.

• Sodium test is needed for the

component design.

• The design method which control

vibration transfer is developed

• The method should be verified by

experiment with sodium.

• Partial trial manufacturing on upper

plenum

• Water test for flow distribution

③③③③Heat transfer capacity• Heat transfer ratio of IHX, which

consists of primary Na in tube and

secondary Na zigzag flow out of tube

• Heat transfer correlation should be

verified by sodium test.


Demonstration testDemonstration test

Sodium experiment Items: Integrated pump-IHX

8



� To simulate shaft rotating conditions

� Rotating speed, hydro-static bearing

shaft and casing rigidity

� Sodium property, temperature

� To simulate flow condition

� Rigid hydraulic design

� Min. flow fitted with 1/1 shaft（Φ300mm）

System & component demonstration test

� To demonstrate tube integrity

� Vibration source (pump)

� Vibration transfer path

� Sodium property and temp.

� To demonstrate heat transfer performance

� Inlet plenum flow distribution

� 2ry sodium zigzag flow

Sodium test with

1/1 shaft length, casing,

bearing

1/10 flow rate

Sodium test with

1/1 shaft, casing, bearing

Sodium test with 1/2 length

tube and min. 8 rows bundle

• For reasonable facility configuration, tube integrity demonstration test and heat transfer

demonstration test should be carried out separately.

1/1 structure

+ 1/10 flow

1/2 length tube

with 50MW

9

1/1 structure

+ 1/10 flow

Scaling of test section: Integrated pump-IHX


3. AtheNa facility

10


Concept of AtheNa facility� Flexible configuration and schedule for experimental

demand

� Shared utilities

� Common utilities, “Mother loop” + several test rigs, “Daughter loops” in

each facility, concept

�“Daughter” test loops are independent of each other

� Several experiments at same time

� Construction and maintenance schedule of test loop is on demand

� Low construction and operation cost

� Flexible use for newly required sodium test

� Another “daughter loop” can be constructed and “Mother loop ”

can supply sodium to them

� Sodium inventory is over 240 ton

� Sodium temperature range is ～570 ℃

11


Test section

Mixed flow type turbo sodium pump

Pump head ～69 mNa

Flow rate ～31.5 m3/min

Axle length 10.7 m

Max. rotating speed 750 rpm

Test section

Single wall straight tube SG

Thermal output ca.10 ＭＷ

Number of tube 37

Steam pressure 19.2 MPa

tube Leffective 29 ｍ

Single wall

Tube material High Cr steel

Mother loop

・Sodium charge & drain

・Sodium purification

・Temperature control

・Gas supply and control

・Experimental data acquisition

Storage tank capacity ca. 240 ton

Max. temperature 250 ℃

SG test loop

Sodium heater power Max. 60 MW

Max. sodium flow rate 20 m3/min

Max. sodium temperature 570 ℃

Steam max. pressure 20 MPa

Pump test loop

Max. sodium flow rate 35 m3/min

Max. sodium temperature 400 ℃

Max. sodium velocity 10 m/sec

Specification of the facility; Component development test

12


50MW partially integrated system

Pump/IHX～DW-SG～steam-water loop

Sodium heater power 60 MW

Flow rate 16.6 m3/min

Sodium velocity in

piping

9.3 m/sec

IHX Secondary Na shell

side zigzag flow

SG Leffective 29 ｍ

Double wall tube

Steam system 19.2 MPa superheated

+ recirculation system

for DHR operation

Demonstration test on whole cooling circuit

RV～Pump/IHX～DW-SG～steam-water loop

+NCDHR system

Reactor vessel 1/3 scaled

Heat source 50～60 MW

The other components are the same as

partially integrated system test.

Test pots Test items

1

Test pot for under

sodium devices

(250 ℃)

• Fuel handling machine ・Fuel transfer

machine

• Under sodium sensors ・ISI devices

• Under sodium repair devices

• Temp. distribution measurements in cover gas

2Long sodium pot

(550 ℃)

• Control rods drive mechanism

• FFD-SV ・Cold trap

3Pot for rotating

plug (550 ℃)

• Temp. distribution measurements in cover gas

• Sodium vapor deposition test for Rotating plug

Open s

pace for

anoth

er

daughte

r te

st lo

ops

Specification of the facility; System & Component Demonstration test

13


Facility view

14

LPG supply

Sodium loops

Steam systems

Storage tanks

Electric supply

Control room

Sodium heater

Transformer

crane

Sodium facility building

Bird’s eye view

from south-west


Inner facility view

15

10MW-SG test rig60MW cooling system demo. rig

Pump test rig

Sodium Pots

Emergency

drain tank

Emergency

drain tank

Mother loop

Storage tanks Inner facilities

Bird’s eye view from south-west


・Dimension：

130 m x 62 m x 55 m

・Total floor area： 11,000 m2

・Electric supply : 7,000 kVA

・Emergency generator：

1,250kVA

・Cranes : 120 & 100 ton

・Thermal output : 60 MW

・Sodium inventory : 240 ton

Sodium HeaterSodium HeaterSodium HeaterSodium Heater

Electric supplyElectric supplyElectric supplyElectric supply

EntranceEntranceEntranceEntrance

S o d iu m S o d iu m S o d iu m S o d iu m L a b o ra to ryL a b o ra to ryL a b o ra to ryL a b o ra to ry

A b o u t A b o u t A b o u t A b o u t 3333 ,,,,4 0 04 0 04 0 04 0 0 mmmm2222

Steam Steam Steam Steam

systemssystemssystemssystems

18m66m46m

62m

Control RoomControl RoomControl RoomControl Room[[[[2222FFFF]]]]

Emergency generatorEmergency generatorEmergency generatorEmergency generator

Sodium TankSodium TankSodium TankSodium Tank

（）（）

100t crane 120t crane

Sodium Tanks

S o d iu m S o d iu m S o d iu m S o d iu m

L a b o ra to ryL a b o ra to ryL a b o ra to ryL a b o ra to ry

55m




Layout of facility

16


4. Current status and SA GIF collaboration

17


Current status of AtheNa Facility [ Building completed in Jan. 2012 ]

Material Test ReactorJMTR

High Temperature Gas ReactorHTTR

Experimental Fast ReactorJOYO

AtheNa

Oarai R&D Center View of AtheNa facility

Sodium heater room

Electric supply room(with emergency generator : 1,250kVA)

Control room

Layout of AtheNa facility








18m66m46m

62m




Sodium Thermal-

Hydraulics Facility

FBR Safety Facilities

Sodium Tech.

Facility

Thermal-Hydraulics

Facility

18

Original plan is suspended due to the Fukushima 1 NPP accident.


On July 19, 2011, JAEC decided to continue the FR cycle technology

development program in the limited range of activities to standardize

international safety criteria and to maintain the technology base level until the

determination of new nuclear energy policy.

On Sept. 27, 2011, JAEC restarted the deliberation process for new Framework

for Nuclear Energy Policy.

- It was suspended after the 3/11 Fukushima accident

- Major issues: Safety, Cost, Nuclear Power and Fuel Cycle Options, Waste

Management, International Perspectives, R&D planning, etc.

Situation of national policy making and FaCT project

In the FaCT project, JAEA is focusing on activities related to the SFR safety

issues and their reflections to the international Safety Design Criteria(SDC).

19


1. Establishment of international SDC for SFR� Re-evaluation on JSFR safety

� Improvements in safety design

� Proposal of “Safety design criteria” to GIF SDC-TF

(accepted at the Beijing meeting on May,2013)

2. Needs for the SDC� Experimental data

� Analytical data

3. Experiments for Severe Accident Counter Measures� Experimental plans for the safety design against severe

accidents

Activities for “the international Safety Design Criteria”

20


Concepts of the Experiments;(1) Safety design policy for severe accident measures

• Measures for In-Vessel-Retention (IVR) have priority.

• For IVR, measures against LOHRS and ATWS should be reinforced.

(2) Candidates of measures against LOHRS• Alternative cooling system must be installed.

• External vessel cooling and internal vessel cooling systems are important candidates.

(3) Phenomena to be investigated for the measures• Heat transfer and thermo-hydraulics in reactor vessel, from

external vessel, and from SG

• Local heat removal characteristics from the damaged core

Scale: ~1/3

Ex-RV

cooling

Air

Sodium

Concept of external vessel cooling test

using AtheNa facility

Experiments for Severe Accident Measures

21

Category FY2012 FY2013 FY2014 FY2015 FY2016 FY2017 FY2018～

1. External vessel cooling

2. Internal vessel cooling

3. Core cooling by SG

4. Experiments for

evaluation

Small scale water test (HTL)

Sodium test (AtheNa)

Small scale water test (HTL)IWF test (PLANDTL)

DHR test (PLANDTL) Integrated test

(AtheNa)

SG DHR test (AtheNa)

Debris bed formation tests

CRGT cooling test (MELT)Degraded core cooling

test (MELT) Large scale test

(AtheNa)


Concept of external vessel cooling test using AtheNa facility

Sto.Tank-1 Sto.Tank-2

Cold-Trap

Exp.Tank

PreheaterHeater

mother loop

Test section loop

Sodium tank [150m3]








18m66m46m

62m




Layout of the test loopEMPEMPEMPEMPEMFEMFEMFEMF

EMPEMPEMPEMP EMFEMFEMFEMFPIPIPIPI

[An example]Ex-RV Decay

Heat Removal Test Section(Scale:ΦΦΦΦ3m)

Test section

[Rough Draft]

22

International collaboration is especially important after the Fukushima 1 NPP accident,

since safety design criteria/measures should be confirmed with objectivity and

crosscheck. An international R&D collaboration on decay heat removal system under

severe situations was proposed and discussed in GIF framework as the first

experimental series in AtheNa facility.


5. Conclusions

23

The JAEA AtheNa facility can serve as an experimental test bed for various

cooling system and components performance tests using large sodium loops.

An international R&D cooperation on decay heat removal system under

severe situations has been proposed and discussed in GIF framework as the

first experimental series in AtheNa facility.

Original plan is suspended due to the Fukushima 1 NPP accident.

Conceptual design and related R&D on Japan Sodium-cooled Fast Reactor

(JSFR) have been carried out since JFY 2006 in Japan. Several innovative

designs of sodium components were established in these design studies and

R&D.

The development plan of JSFR includes large-scale sodium experiments

of such sodium components and system demonstrations.


Thank you for

your attention.

24

advanced technology experiment sodium facility (athena

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