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Update on IFE Safety Work for ARIES. David Petti Fusion Safety Program ARIES e-meeting October 17, 2001. Several safety issues for IFE designs are being studied. Target fabrication safety and reliability issues Risk assessment accident-initiating events Coolant hazards (Sn, Pb, Sn-25Li) - PowerPoint PPT Presentation
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Idaho National Engineering and Environmental Laboratory
Update on IFE Safety Work for ARIES
David PettiFusion Safety Program
ARIES e-meetingOctober 17, 2001
Idaho National Engineering and Environmental Laboratory
Several safety issues for IFE designs are being studied• Target fabrication safety and reliability issues• Risk assessment accident-initiating events• Coolant hazards (Sn, Pb, Sn-25Li)
– Chemical reactivity– Chemical toxicity– Radiological hazards
• Aerosol considerations for chamber clearing
Idaho National Engineering and Environmental Laboratory
Manufacturing industry input for IFE target fabrication• INEEL and GA personnel visited Micron Technology
(Boise, ID) on July 18 to gather information about manufacturing processes for precision, high quality, large scale production.
• Highlights of the Micron facility:– produces on the order of 400,000 chips/day– clean room facilities are large and expensive (i.e.,
$3k/foot2). – 1.5 mile tour to visit the manufacturing stations
• Micron staff members were enthused about potential collaboration(s) to support IFE target manufacture.
Idaho National Engineering and Environmental Laboratory
Industry input on manufacturing quality assurance• Quality Assurance data about the Micron facilities:
– an initial production run may have 50% defects, while a mature run has less than 10% defects.
– batches from an initial production run are tested up to 130 hrs while mature runs are tested up to 10 hrs.
– an estimated four to five “end user product” returns per million units distributed.
– facility support services are tightly controlled to maintain manufacturing quality.
– electrostatic suppression and discharge are very important for maintaining high-quality production.
Idaho National Engineering and Environmental Laboratory
Accident initiating events are being compiled for IFE designs• Current initiator work is focused on the SOMBRERO
design.– SOMBRERO is representative of dry wall, laser driver
IFE design concepts• A master logic diagram (MLD) for SOMBRERO has been
drafted and is under review. The MLD is a plant-level fault tree of potential hazardous releases.
• An MLD for the HYLIFE II plant design has been initiated and will be completed later this year.– HYLIFE II is representative of liquid wall, ion beam
driver IFE design concepts
Idaho National Engineering and Environmental Laboratory
Coolant hazards: chemical reactivity• Queries of the HSC chemistry database program show:
– molten Pb, Sn, and Sn-25Li exothermically react with air and potentially result in limited aerosol generation;
– liquid Sn exothermically forms SnO2 in abundant air or SnO in limited air;
– at low temperatures (150 to 550°C), liquid Pb in air exothermically forms gaseous Pb2O3. Above 550°C, the gas dissociates into PbO gas and PbO2. The PbO2 will potentially form aerosol;
• Li and Sn individually react in air to form chemically toxic species, thus the same behavior is anticipated for Sn-25Li in air.
Idaho National Engineering and Environmental Laboratory
Coolant hazards: chemical reactivity (cont)
• Li dehydrates concrete: reaction rates are low in the 200°C range and increase in the 400°C range.
• In the 400 °C range, other liquid metals will also dehydrate concrete. Thus safety design provisions are required.
• Li reacts in air to form Li2O and generate 3-10%wt respir-able aerosol. LiOH aerosol is also formed if water vapor is present in the air (HEDL TME 80-79; HEDL TME 85-25)
• Molten Pb-Li and Sn-Li will react with water to release hydrogen gas (M. H. Anderson, 14th TOFE).
Idaho National Engineering and Environmental Laboratory
Coolant hazards: chemical toxicity• Li, Pb, Sn, and Sn-25Li have un-irradiated chemical
safety concerns.• DOE has established Temporary Emergency Exposure
Levels (TEELs) for aerosol inhalation of chemical substances by the general public.
• The DOE-Idaho Operations Office recommends TEEL-2 as a prudent 1-hour maximum exposure level for public safety.
• DOE-HQ has not yet released guidance on exposure levels for chemical releases in energy research.
Idaho National Engineering and Environmental Laboratory
TEELs for candidate IFE coolantsMaterial TEEL-0
(mg/m3)TEEL-1(mg/m3)
TEEL-2(mg/m3)
TEEL-3(mg/m3)
Tin(Sn)
2 6 10 100
Tin oxide(SnO)
2 6 10 100
Lithium(Li)
10 30 50 500
Lithiumoxide(Li2O)
-- -- AIHA cites1 mg/m3 forworkers =
TEEL-2
--
Lithiumhydroxide
(LiOH)
0.05 0.15 1 100
Lead(Pb)
0.05 0.15 0.25 100
Lead oxides(PbO and
PbO2)
0.05 0.05 0.05 100
TEEL LevelHealthEffects
nohealtheffects
mild,transienteffects
serious,transienteffects
life can bethreatenedpast 1 hourexposure
note: TEELs are from report WSMS-SAE-00-0266, revision 17m, January2001. See also WSRC-TR-98-00080, “Methodology for Deriving TEELs,”April 1998.
Idaho National Engineering and Environmental Laboratory
Coolant hazards: radiological concerns• A radiological-based analysis of the coolants focused on
five factors:– Decay heat generation: influences accident response– Contact dose (gamma): influences worker safety and
maintenance– Vapor pressure: volatility under air in steam ingress
condition– Radiotoxicity: identifies the isotopes whose activity
levels produce radiation concerns– Class C waste: identifies materials that can meet the
low level waste criteria
Idaho National Engineering and Environmental Laboratory
Decay heat comparison
From: C.B.A. Forty et. al., Handbook of Fusion Activation Data, Part 1, AEA FUS 180, May 1992 and Part 2, AEA FUS 232, May 1993, AEA Technology Fusion, Culham Laboratory, Abingdon, Oxon.
10-14 10-12 10-10 10-8 10-6 10-4 10-2 100
Sn
Sn-25Li
V
Pb
Li (w/o H3)
100 years10 years1 hour
Decay Heat at the First Wall (W/g)
Idaho National Engineering and Environmental Laboratory
Contact dose (gamma) comparison
From: C.B.A. Forty et. al., Handbook of Fusion Activation Data, Part 1, AEA FUS 180, May 1992 and Part 2, AEA FUS 232, May 1993, AEA Technology Fusion, Culham Laboratory, Abingdon, Oxon. R. Haange et al., “Remote Handling Maintenance of ITER,” Fusion Energy 1998, Proceedings of the 17th IAEA Fusion Energy Conference, Yokohama, Japan, 18-24 October 1998, 3, pgs 965-972
10-14 10-12 10-10 10-8 10-6 10-4 10-2 100 102 104
Sn
Sn-25Li
Pb
Li (w/o H3 )
100 years10 years
Contact Dose at the Shield (Sv/hr)
10CFR835upper limithands-on
1 Sv = 100 Rem
DOE1098-99upper limithands-on
Snowmass-99remote handling
(2628 Sv/lifetime)
R. HaangeRemote Handling
(8 x 109 Sv/lifetime)
Idaho National Engineering and Environmental Laboratory
Vapor pressure comparison
From: The Characterization of High-Temperature Vapors, edited by J.L. Margrave, John Wiley & Sons, Inc. 1967. Sn-25Li data from R.A. Anderl et al., “Vaporization Properties of Sn-25at%Li Alloy,” Proceedings of the 10th International Conference on Fusion Reactor Materials, October 14-19, 2001, Baden-Baden, Germany.
10-9
10-7
10-5
10-3
10-1
400 600 800 1000 1200 1400
SnPbLi25Li-75Sn
Vap
or
Pre
ssu
re (
kPa)
Temperature (C)
Sn-25LiPbLi Sn
Idaho National Engineering and Environmental Laboratory
Radiotoxicity of Liquid Metals
From: C.B.A. Forty et. al., Handbook of Fusion Activation Data, Part 1, AEA FUS 180, May 1992 and Part 2, AEA FUS 232, May 1993, AEA Technology Fusion, Culham Laboratory, Abingdon, Oxon.
Sn
Sn-25Li
Pb
Li (w/o H3) 100 years
1 years
10-6 10-4 10-2 100 102 104 106 108 1010 1012
Specific Activity at the Shield (Bq/kg)
Sn-119m (t1/2
= 0.8 yr)
Ti-204 (t1/2
= 3.8 yr)
Pb-205 (t1/2
= 1.4E7 yr); Bi-207 (t1/2
= 38.0 yr)
Sn-121m (t1/2
= 50.1 yr)
Sn-119m (t1/2
= 0.8 yr)
Sn-121m (t1/2
= 50.1 yr)
Idaho National Engineering and Environmental Laboratory
1
H
3
Li
4
Be
11
Na
12
Mg
19
K
20
Ca
21
Sc
22
Ti
23
V
37
Rb
39
Y
40
Zr
41
Nb
55
Cs
56
Ba
57
La
73
Ta
24
Cr
42
Mo
74
W
25
Mn
26
Fe
28
Ni
46
Pd
47
Ag
30
Zn
48
Cd
5
B
31
Ga
49
In
6
C
14
Si
32
Ge
50
Sn
15
P
33
As
8
O
52
Te
9
F
53
I
2
He
10
Ne
36
Kr
54
Xe
69
Tm
68
Er
66
Dy
65
Tb
63
Eu
60
Nd
59
Pr
18
Ar
no stable
isotopes
83
Bi
82
Pb
81
Tl
79
Au
77
Ir
no stable
isotopes
70
Yb
72
Hf
27
Co
45
Rh
44
Ru
13
Al
7
N
17
Cl
16
S
29
Cu
34
Se
38
Sr
51
Sb
75
Re
76
Os
78
Pt
80
Hg
58
Ce
62
Sm
35
Br
64
Gd
67
Ho
71
Lu
unlimited 10% 1% .1% .01% .001% .0001%
Top half of box: hard spectrum Bottom half of box: soft spectrum
.00001%
Limits on Elements for Class C Waste Qualification
From: S.J. Piet, et al., “Initial Integration of Accident Safety, Waste Management, Recycling, Effluent, and Maintenance Considerations for Low-Activation Materials”, Fusion Technology, Vol. 19, Jan. 1991, pp. 146-161. Assumes 5 MW/m2 for 4 years; and E. T. Cheng, “Concentration Limits of Natural Elements in Low Activation Materials”, presented at ICFRM-8, Sendai, Japan,October 1997
Idaho National Engineering and Environmental Laboratory
Inventory-based radiotoxicity
Metric(Sv) = [Inventory (Ci)* Radiotoxicity (Sv/Ci)]
1.00E-01
1.00E+00
1.00E+01
1.00E+02
1.00E+03
1.00E+04
Gold Tungsten Lead Platinum Palladium Silver
Target
Chamber FW
Inventory based Dose Metric (Sv) for Laser IFE
1.00E-01
1.00E+00
1.00E+01
1.00E+02
1.00E+03
1.00E+04
1.00E+05
Gold/Gd Hg Ta Hg/W/Cs Pb/Hf Pb/Ta/Cs
Target
Chamber FW
Inventory based Dose Metric (Sv) for Heavy Ion Fusion
Idaho National Engineering and Environmental Laboratory
Aerosol considerations for chamber clearing
• Issues of aerosol generation and transport– Aerosol conservation model– Representative nucleation and growth rates– Particle transport– Particle deposition
• Future work
Idaho National Engineering and Environmental Laboratory
Aerosol conservation model• Evolution of the aerosol size distribution is governed
by the aerosol General Dynamic Equation (GDE):
• This equation demonstrates aerosol particle conservation, where n is the number of particles per unit particle volume per unit gas volume.
n
tn D n c n
n
t
n
t
n
tg ro w th g ro w th
C onvectiv e D iffu s ionand T ran sport
hom o hetro coag
P artic le G row th andC oagu la tio n
, ,
Idaho National Engineering and Environmental Laboratory
Homogeneous nucleation rate of Pb:
Nucleation rate and critical radius of Pb at various saturation temperatures
Time required to form 1015 Pbparticles/m3
(where coagulation becomes increasingly important)
(these saturation ratios are comparable to those achievable in cloud chambers)
10 14
10 16
10 18
10 20
10 22
10 24
10 26
10 28
10 30
10 32
10 34
10 36
10 38
0.01
0.1
1
10
1 10 100
Critica
l Ra
diu
s (nm
)(dashed curves)
HM
G N
ucl
ea
tion
Ra
te (
#/m
3 /s)
(sol
id c
urve
s)
Saturation Ratio
1500 K
2000 K
2500 K
3000 K
1000 K
1500 K
2000 K2500 K
3000 K
3500 K
3500 K
10 -4
10 -2
10 0
10 2
10 4
10 6
0 2 4 6 8 10
Nuc
leat
ion
Tim
e (µ
s)
Saturation Ratio
1500 K
1750 K
2000 K
2500 K
3000 K
Clearing Time (0.1 sec.)
Idaho National Engineering and Environmental Laboratory
Heterogeneous growth and coagulation rate of Pb:Time needed for particles in saturated
vapor to increase volume by 10%Time required for 1 µm dust particles
to change total number by 10%
• Dust particle concentrations generated from homogeneous nucleation are sufficiently large so that particle growth and coagulation occur faster than chamber clearing times
10 0
10 1
10 2
10 3
10 4
10 5
10 6
0 20 40 60 80 100
Con
dens
atio
n T
ime
(µs)
Saturation Ratio
1500 K
Clearing Time- 0.1 sec.
3500 K
3000 K
2500 K
2000 K
10 -6
10 -5
10 -4
10 -3
10 -2
10 -1
10 0
10 1
10 13 10 14 10 15 10 16 10 17 10 18 10 19 10 20
Tim
e fo
r 10
% C
hang
e (s
ec.)
Initial Number Density (#/m 3)
Clearing Time (0.1 sec.)
Est
imat
ed p
artic
le c
once
ntra
tion
for
hom
ogen
eous
nuc
leat
ion 1000 K
3500 K
Idaho National Engineering and Environmental Laboratory
Homogeneous nucleation rate of W:
Nucleation rate and critical radius of W at various saturation temperatures
Time required to form 1015 Wparticles/m3
(where coagulation becomes increasingly important)
(these saturation ratios are comparable to those achievable in cloud chambers)
10 18
10 20
10 22
10 24
10 26
10 28
10 30
10 32
10 34
10 36
10 38
0.01
0.1
1
10
1 10 100
HM
G N
ucl
ea
tion
Ra
te (
#/s
/m3 )
Critica
l Ra
diu
s (nm
)
Saturation Ratio
4000 K
6000 K
7000 K
4500 K
5000 K
3500 K
3500 K
7000 K
(dashed curves)
10 -4
10 -2
10 0
10 2
10 4
10 6
0 2 4 6 8 10
Nuc
leat
ion
Tim
e (µ
s)
Saturation Ratio
4000 K
6000 K
7000 K
4500 K5000 K
3500 K
Clearing Time (0.1 sec)
Idaho National Engineering and Environmental Laboratory
Heterogeneous growth and coagulation rate of W:Time needed for particles in saturated
vapor to increase volume by 10%Time required for 1 µm dust particles
to change total number by 10%
10 0
10 1
10 2
10 3
10 4
10 5
10 6
0 20 40 60 80 100
Con
dens
atio
n T
ime
(µs)
Saturation Ratio
Clearing Time- 0.1 sec.
6000 K
5000 K
4500 K
4000 K
7500 K
10 -6
10 -5
10 -4
10 -3
10 -2
10 -1
10 0
10 1
10 13 10 14 10 15 10 16 10 17 10 18 10 19 10 20
Tim
e fo
r 10
% C
hang
e (s
ec.)
Initial Number Density (#/m 3)
Clearing Time (0.1 sec.)
Est
imat
ed p
artic
le c
once
ntra
tion
for
hom
ogen
eous
nuc
leat
ion 3500 K
7500 K
• Dust particle concentrations generated from homogeneous nucleation are sufficiently large so that particle growth and coagulation occur faster than chamber clearing times
Idaho National Engineering and Environmental Laboratory
Convective diffusion and transport
• The diffusive transport time constant is• for a characteristic gradient length L = 1 cm and D ~ 10-5
m2/s, diff = 10 s. This value decreases when particle slip is considered.
• Migration velocities for gravitational settling, electrostatic mobility, and thermophoretic forces yield time constants migration ~ L/Ci ~ 1 - 10 s.
• These mechanisms are of less importance for inter-shot aerosol transport than for long-term transport associated with accident analysis
d iffLD2
n
t nv Dn
c n
Idaho National Engineering and Environmental Laboratory
Particle deposition
• Deposition via diffusive and/or migratory transport of particles are secondary effects for inter-shot aerosol transport
• inertial deposition and turbulent deposition are important for inter-shot aerosol transport because they are responsible for placing particles at undesired locations, such as on final optics or in ducts.
J
wall Dn
c migration
c inertial
c turbulent n
Idaho National Engineering and Environmental Laboratory
Future work for aerosol formation• Aerosol model requires local state properties (T,P) for
determining nucleation and growth rates. Flow field is also needed for particle convection and deposition
• Solve within Hydrodynamic Chamber Model• Modify existing INEEL fluids/aerosol model to
simulate a dry-wall IFE chamber for the purpose of scoping studies
• Experimental benchmarking
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