Pre-irradiation Characterization of Beryllium for High ...Boudewijn Pijlgroms a NRG Petten, the...
Transcript of Pre-irradiation Characterization of Beryllium for High ...Boudewijn Pijlgroms a NRG Petten, the...
-
Status of the high Status of the high fluencefluence irradiation of irradiation of ceramic pebbles in the HICU projectceramic pebbles in the HICU project
Hans Hegeman, Jaap van der Laan , Kees Beemsterboer, Sander Kamer and
Boudewijn Pijlgroms
a NRG Petten, the Netherlands
Ceramic Breeder Blanket Interactions CBBI-13, 1 December
-
OutlineOutline
Objectives of the high fluence irradiation Nuclear characteristicsTest matrix and designThermal design of the irradiation devicePre-irradiation characterisationOutlook
-
ObjectivesObjectives
“Investigation of a) the impact of neutron spectrum and b) the influence of constraint conditions
on the thermo-mechanical behavior of breeder pebble-beds in a high fluence irradiation”
HICU Fluence (E>0.1 MeV 1026 n/m2) 1.5
Fluence (E>1 MeV 1026 n/m2) 0.7 6Li enrichments Li4SiO4 (%) 0.06, 7.5, 20 6Li enrichments Li2TiO3 (%) 0.06, 11, 30 6Li Burnup (%) 0.74 - 13
Neutron damage (dpa) 20-25
Temperatures (°C) 600-650 750-800
-
Irradiation characteristicsIrradiation characteristics
0 2 4 6 8 10 120
10
20
30
40
50
0.06% unshielded
7.5% unshielded7.5% shielded
20% shielded
EXOTIC 7, 8
DEMO blanket 1 FPY
Dis
plac
emen
t dam
age
in O
Si (d
pa)
Total Lithium burnup in OSi (%)
Near first wall
Near back plate
DEMO blanket 20.000 hrs
-
Spectrum effect in Spectrum effect in OrthosilicateOrthosilicateEffect is calculated for the actual vertical location of the specimen
Specimen 7.1 with Othosilicate 7.5% 6LiSpecimen 8.1 with Othosilicate 20% 6Li enriched
10-3 10-2 10-1 100 101 102 103 104 105 106 107
1012
1013
1014
Neu
tron
Flux
energy (eV)
OSi 7.5% shielded OSi 20% shielded OSi 7.5% OSi 20%
-
Spectrum effect in Spectrum effect in MetatitanateMetatitanateEffect is calculated for the actual vertical location of the specimen
Specimen 5.1 with Metatitanate 7.5% 6LiSpecimen 4.1 with Metatitanate 30% 6Li enriched
10-3 10-2 10-1 100 101 102 103 104 105 106 1071011
1012
1013
1014
Neu
tron
Flux
energy (eV)
MTi 7.5% shielded MTi 30% shielded MTi 7.5% MTi 30%
-
Test MatrixTest Matrix
NRG-ID. Suppl. % enrichment High Constraint High T
High Constraint Low T
Low ConstraintHigh T
Low ConstraintLow T
Total
NRG-126 FzK OSi 20 2 1 1 4 NRG-125 FzK OSi 7.5 2 1 1 1 5 NRG-129 FzK OSi 7.5 1 1 NRG-124 FzK OSi 0.06 1 1 2 5 1 3 3 12 NRG-120 CEA MTi 30 2 1 1 4 NRG-119 CEA MTi 11 2 1 1 1 5 NRG-118 CEA MTi 0.06 1 1 2 NRG-121 CEA MTi 7.5 1 1 2 NRG-122 CEA MTi 7.5 1 1 2 NRG-123 CEA MTi 7.5 1 1 2 NRG-130 CEA MTi 7.5 1 1 2 NRG-131 CEA MTi 30 1 1 2
6 2 7 6 21 NRG-115 JAERI MTi 31 1 1 1 3 NRG-116 JAERI MTi-5% 31 1 1 1 1 4 NRG-117 JAERI MTi-10% 31 1 1 1 3 NRG-127 JAERI MTi 7.5 1 1
3 1 4 3 11 Total Total 14 4 14 12 44 HiCon 18 LoCon 26
-
Capsule designCapsule design
8 drums loaded with pebble stacksEach drum is separated by heat barriers/radiation shieldsCentral discs for determination of nuclear heating (gamma)On-line tritium monitoring (entire capsule) including moisture
First containmentSecond containment
(9x4
7+7x
10+1
5)50
8
Drum 8: 650-850°C
Drum 7: 850°C+ dosimeterset
Drum 6: 850°C
Drum 5: 850°C+ dosimeterset
Drum 4: 850°C
Drum 2: 650°C
Drum 3: 850°C+ dosimeterset
5981
5
300
CL-core
233
10(7
x)47
(9x)
3
-
Design of the irradiation capsuleDesign of the irradiation capsule
Stainless steel, 0,9mm tube
1,9mm Cadmium/Hafnium
Stainless steel, 0,2mm tube
QUATTRO, ID Ø29 mm
(Ø28,8) Stepped OD containment)
Ø22,8H7 (ID containment)
Eurofer cladding, Ø4xØ5 mm. 51°
(0,55)
7
stc15,2
Vanadium alloy 'drum':
Eurofer cladding, Ø9 x ±Ø11 mm.
Tc holes: Ø1,1 mm
28°
R0,2
stc9,5
22°
4,92
R large spec
R small spec 3
R small spec 2
R small spec 1
Ø11,1H7
R6,1
51°
Ø6,1H7(3x)
Ø22
,8g6
(OD
dru
m)
Gas tube 2,5x1,7mm
Thermocouples
123
4
-
Location of the ceramic pebble stacksLocation of the ceramic pebble stacks
Tccenter
Tccladdin
g spec.materialT
(central)P (n,a)(W/cc)
1 1.2 mti-31-10% NRG-117 JAERI 650 12.6DRUM 2.2 osi-7.5 NRG-125 EU-FZK 650 4.4
1 1 1.3 mti-31 NRG-115 JAERI 650 12.31.4 mti-31-5% NRG-116 JAERI 650 11.81.5 mti-31-10% NRG-117 JAERI 650 10.8
1 2.1 mti-11 NRG-119 EU-CEA 650 6.7DRUM 1.1 mti-ref+++ NRG-130 EU-CEA 650 5.9
2 1 9.3 mti-ref NRG-121 EU-CEA 650 4.72.4 mti-11 NRG-119 EU-CEA 650 7.42.5 mti-0.06 NRG-118 EU-CEA 650 0.5
1 1 4.1 mti-30 NRG-120 EU-CEA 800-850 18.6DRUM 4.2 mti-30 NRG-120 EU-CEA 800-850 20.9
3 1 3.3 mti-31 NRG-115 JAERI 800-850 22.93.4 mti-31-5% NRG-116 JAERI 800-850 21.53.5 mti-31-10% NRG-117 JAERI 800-850 20.5
9.1 mti-31-10% NRG-117 JAERI 800-850 21.7DRUM 1 9.2 mti-ref+ NRG-122 EU-CEA 800-850 6.4
4 5.5 mti-ref++ NRG-123 EU-CEA 800-850 7.01 6.4 osi-7.5 NRG-125 EU-FZK 800-850 12.2
4.5 mti-ref+ NRG-122 EU-CEA 800-850 8.7
-
Location of the ceramic pebble stacksLocation of the ceramic pebble stacks2
5.1 mti-ref+++ NRG-130 EU-CEA 800-850 9.4DRUM 1 5.2 osi-7.5+ NRG-129 EU-FZK 800-850 12.3
5 1 5.3 osi-20 NRG-126 EU-FZK 800-850 24.95.4 mti-30 NRG-120 EU-CEA 800-850 28.34.3 mti-30 NRG-120 EU-CEA 800-850 34.7
1 1 6.1 osi-7.5 NRG-125 EU-FZK 800-850 13.0DRUM 6.2 osi-7.5 NRG-125 EU-FZK 800-850 13.0
6 1 6.3 be-peb 0 EU-Be 800-850 0.04.4 mti-0.06 NRG-118 EU-CEA 800-850 1.46.5 osi-0.06 NRG-124 EU-FZK 800-850 3.7
1 1 7.1 mti-11 NRG-119 EU-CEA 800-850 12.8DRUM 7.2 mti-11 NRG-119 EU-CEA 800-850 12.2
7 1 7.3 mti-ref NRG-121 EU-CEA 800-850 9.87.4 mti-11 NRG-119 EU-CEA 800-850 13.07.5 mti-7.5 NRG-127 JAERI 800-850 8.8
1 1 8.1 osi-20 NRG-126 EU-FZK 800-850 20.6DRUM 8.2 osi-20 NRG-126 EU-FZK 800-850 19.4
8 1 9.4 mti-ref++ NRG-123 EU-CEA 650 6.88.4 osi-7.5 NRG-125 EU-FZK 650 11.78.5 osi-0.06 NRG-124 EU-FZK 650 3.2
1 3.2 mti-31-5% NRG-116 JAERI 800-850 24.7DRUM 3.1 mti-31 NRG-115 JAERI 800-850 19.6
9 1 8.3 mti-ref++++ NRG-131 EU-CEA 650 27.39.5 osi-20 NRG-126 EU-FZK 650 22.52.3 mti-30 NRG-120 EU-CEA 650 21.9
4 20
-
Capsule designCapsule design
Thermocouple locations Vanadium drum
-
Cadmium shield manufacturingCadmium shield manufacturing
Fabrication route selected: uniaxial compression of cadmium/hafnium ring inside two concentric tubesThin cladding on the inside, containment tube on the outside
Gas gaps
-
ThermalThermal Design of HICUDesign of HICU
2D and 3D analysesTemperature limits for Cadmium (nor melting allowed)Thermocouples included
-
Thermal Design of HICU (2)Thermal Design of HICU (2)
Results for central drum with all specimens at 850°CResults for lowest drum 9, with large pebble stack at 850°C and small stacks at 650°C
-
Thermal Design of HICU (3)Thermal Design of HICU (3)
3D models required due to asymmetry and stress analysis
-
Thermal Design of HICU (4)Thermal Design of HICU (4)
High thermal gradients within the pebble stacks due to the low thermal conductivity of the ceramic breeder
Central drum Bottom drum
-
Cross section temperaturesCross section temperatures
-
Cross section temperatures (2)Cross section temperatures (2)
-
Ther
moc
oupl
e di
strib
utio
nTh
erm
ocou
ple
dist
ribut
ion
-
PrePre--stressing pebble stacksstressing pebble stacks
0
0.05
0.1
0.15
0.2
0.25
0.3
0.35
0.4
0 1000 2000 3000 4000 5000 6000 7000 8000 9000
time (sec)
com
pres
sion
(mm
)
0
20
40
60
80
100
120
140
160
180
200
load
(N)
displacement for 3 MPadisplacement for 2 MPaload for 3 MPaload for 2 MPa
removeradialconstraintload control
displacement control
spotwelding lid
-
PrePre--stressing pebble stacksstressing pebble stacks
After pre-stress
heated Pebble-stack
persen tot 3 MPa + holdtime
0
20
40
60
80
100
120
140
160
180
200
0 0.05 0.1 0.15 0.2 0.25 0.3 0.35 0.4
displacement (mm)
load
(N)
3 MPa test2 MPa test
-
XrayXray tomography of the pebble stackstomography of the pebble stacks
Xray tomography enhances the PIEXray tomography results could be used for thermo-mechanical models -> pebble size and location, number of contact point
-
Measurement of size distributionMeasurement of size distribution
Example from beryllium irradiation (HIDOBE)Pre-stress at 1 MPa, strain approx. 0.7%
11448 pebblesAv. Size 0.514 mm Roundness 1.12
1976 pebblesAv. Size 0.962 mm Roundness 1.12
-
OutlookOutlook
Loading of the specimensCharacterisation of the pebbles in December/JanuaryX-ray tomography January
Manufacturing irradiation rigStarted ordering components: some rare earth materials (Cd and Hf) have delivery times > 4 monthsFinal rig drawing are preparedDrum machining to start in December/JanuaryLoading of the drums and assembly February
Final design and safety report is in preparationAccount for HUE to LUE conversion and HFR operational requirements
Status of the high fluence irradiation of ceramic pebbles in the HICU projectOutlineObjectivesIrradiation characteristicsSpectrum effect in OrthosilicateSpectrum effect in MetatitanateTest MatrixCapsule designDesign of the irradiation capsuleLocation of the ceramic pebble stacksLocation of the ceramic pebble stacksCapsule designCadmium shield manufacturingThermal Design of HICUThermal Design of HICU (2)Thermal Design of HICU (3)Thermal Design of HICU (4)Cross section temperaturesCross section temperatures (2)Thermocouple distributionPre-stressing pebble stacksPre-stressing pebble stacksXray tomography of the pebble stacksMeasurement of size distributionOutlook