PAUL SCHERRER INSTITUT

WP-11 Meeting, ESS, Lund, 2012 ,05.07 Y. Dai / PSI

WP 3 status and follow upWP 3 status and follow up

Yong Dai Yong Dai

Paul Scherrer Institut, 5232 Villigen PSI, SwitzerlandPaul Scherrer Institut, 5232 Villigen PSI, Switzerland

WP 11 Meeting, ESS, Lund, 2012.05.08

PAUL SCHERRER INSTITUT

WP-11 Meeting, ESS, Lund, 2012 ,05.07 Y. Dai / PSI

OutlineOutline

Material issues for the target Present status of WP-3 Short term plan Long term plan

PAUL SCHERRER INSTITUT

WP-11 Meeting, ESS, Lund, 2012 ,05.07 Y. Dai / PSI

Material issuesMaterial issues

Be

WSS316LN

Al6061

PAUL SCHERRER INSTITUT

WP-11 Meeting, ESS, Lund, 2012 ,05.07 Y. Dai / PSI

Material issuesMaterial issues

W- target slabs

Target Shroud

Reflector Ref./Mod. container

Material Pure W SS 316LN? Be SS316L / Al6061

T-range 20–700°C 20-450°C 20-?? ??

Max. Stress 140 MPa ?? ?? ??

Max dpa/y 5 ?? ?? ??

Max He/y 500?appm ?? ?? ??

Operation parameters of various components (to be updated)

PAUL SCHERRER INSTITUT

WP-11 Meeting, ESS, Lund, 2012 ,05.07 Y. Dai / PSI

Material issuesMaterial issuesOperation parameters of various components (to be confirmed)

PAUL SCHERRER INSTITUT

WP-11 Meeting, ESS, Lund, 2012 ,05.07 Y. Dai / PSI

Material issuesMaterial issuesOperation parameters of various components (to be confirmed)

PAUL SCHERRER INSTITUT

WP-11 Meeting, ESS, Lund, 2012 ,05.07 Y. Dai / PSI

Material issuesMaterial issues

W- target slabs

Target Shroud

Reflector Ref./Mod. container

Material Pure W SS 316LN? Be (Pb) SS316L / Al6061

T-range 20–700°C 20-500°C 20-?? ??

Max. Stress

change

140 MPa ?? ?? ??

Max dpa/y 5 ?? ?? ??

Max He/y 500?appm ?? ?? ??

Operation parameters of various components (to be updated)

PAUL SCHERRER INSTITUT

WP-11 Meeting, ESS, Lund, 2012 ,05.07 Y. Dai / PSI

Material issuesMaterial issues

W- plates SS316LN Shroud

Be Reflector Al6061 Mod. container

Ther. fatigue To be considered

To be considered

??

Irr embrittle. Yes Yes Yes Yes

Irr swelling To be considered

?? ??

Oxidation

/ Erosion

To be considered

Materials issues of various components (to be updated)

PAUL SCHERRER INSTITUT

WP-11 Meeting, ESS, Lund, 2012 ,05.07 Y. Dai / PSI

Present activitiesPresent activities Collect existing data, prepare TDR

PAUL SCHERRER INSTITUT

WP-11 Meeting, ESS, Lund, 2012 ,05.07 Y. Dai / PSI

Present activitiesPresent activities Collect existing data, prepare TDR

Severe cracking of the tungsten due to the thermal gradients.Nelson et al. IWSMT-10, JNM, in press.

PAUL SCHERRER INSTITUT

WP-11 Meeting, ESS, Lund, 2012 ,05.07 Y. Dai / PSI

Present activitiesPresent activities Start experiments on reference tungsten and W-alloys

Tungsten alloy: IT180 in helium with 5% oxygen for 2.5 hours.

S. Iyengar, E. Malm, Lund Technical University

PAUL SCHERRER INSTITUT

WP-11 Meeting, ESS, Lund, 2012 ,05.07 Y. Dai / PSI

Short term (2012-13) planShort term (2012-13) plan Investigations on reference tungsten material

Characterization of as-received materialsDensity, Metallurgy, Hardness

Mechanical testing at ESS relevant temperaturesTensile, Fatigue, Bend

Microstructural analysesTEM: as-received, after testingSEM: fracture behaviour

Erosion experiments at KIT( tbd)

Oxidation experiments at LTU (tbd)

PAUL SCHERRER INSTITUT

WP-11 Meeting, ESS, Lund, 2012 ,05.07 Y. Dai / PSI

Short term (2012-13) planShort term (2012-13) plan Investigations on irradiated tungsten material

Mechanical testing and Microstructural analyses of STIP-II (@JAEA) and STIP-V (@PSI) samplesTensile, Hardness, Metallurgy, TEM, SEM, gamma-measurements etc.

PAUL SCHERRER INSTITUT

WP-11 Meeting, ESS, Lund, 2012 ,05.07 Y. Dai / PSI

Materials STIP-ISTIP-I STIP-IISTIP-II STIP-IIISTIP-III STIP-IVSTIP-IV STIP-VSTIP-V STIP-VISTIP-VI

Austenitic Austenitic steelssteels

≤ 12 dpa

≤ 400°C

≤ 20 dpa

≤ 400°C

≤ 20 dpa

≤ 400°C

≤ 25 dpa

< 400°C(?)

25 dpa

400°C

20 dpa

600°C

FM steelsFM steels

(FMS)(FMS)

≤ 12 dpa

≤ 360°C

≤ 20 dpa

≤ 400°C

≤ 20 dpa

≤ 600°C

≤ 25 dpa

< 600°C(?)

20 dpa

400°C

20 dpa

600°C

FMS-ODSFMS-ODS ≤ 20 dpa

< 400°C

≤ 20 dpa

≤ 600°C

≤ 25 dpa

< 600°C(?)

20 dpa

600°C

20 dpa

600°C

Ni-alloyNi-alloy ≤ 12 dpa

≤ 400°C

≤ 20 dpa

≤ 400°C

20 dpa

600°C

Al-alloyAl-alloy ≤ 3 dpa

≤ 60°C

≤ 6 dpa

≤ 60°C

Zr-alloyZr-alloy ≤ 22 dpa

< 300°C

≤ 35 dpa

< 300°C

≤ 35 dpa

< 300°C

TaTa ≤ 30 dpa

≤ 350°C

Yes (no more

available)

Mo, W, Mo, W, alloysalloys

Yes (no results)

Yes (no results)

Yes

800°C

Yes

500°C

SiCf/SiC, SiCf/SiC, CMCCMC

Yes (to be tested)

Yes Yes

800°C

Overview of materials irradiated in STIP Overview of materials irradiated in STIP

PIE has been partially done.

PAUL SCHERRER INSTITUT

WP-11 Meeting, ESS, Lund, 2012 ,05.07 Y. Dai / PSI

Short term (2012-13) planShort term (2012-13) plan Investigations on irradiated tungsten material

Mechanical testing and Microstructural analyses of STIP-II (@JAEA) and STIP-V (@PSI) samplesTensile, Hardness, Metallurgy, TEM, SEM, gamma-measurements etc.

Investigations on irradiated structural materials

Fatigue testing on irradiated SS 316LN samples

PAUL SCHERRER INSTITUT

WP-11 Meeting, ESS, Lund, 2012 ,05.07 Y. Dai / PSI

Long term (2014-) planLong term (2014-) plan Irradiate W samples for ESS, CSNS, etc

4 5

1

234

56

78

6

3

1 2

Proton beam

W samples considered:R1: 10 W bullets with Ta, Zy-2, SS

cladding, HIP’edR2: 10 W bullets with Ta, Zy-2, SS

cladding, canedR3: 1 W rod with Zy-2 cladding,

canned, with 2 TCsR4: Bend, Tensile, TEM samplesin 2 surface

conditions, in HeR5: Bend, Tensile, TEM samples in 2 surface conditions, in He-5%H

Irradiate W samples in the next SINQ targetIrradiation: 2013-2014, PIE: 2016 -