idaho national engineering and environmental laboratory update on ife safety work for aries david...

Idaho National Engineering and Environmental Laboratory

Update on IFE Safety Work for ARIES

David PettiFusion Safety Program

ARIES e-meetingOctober 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)

– Chemical reactivity– Chemical toxicity– Radiological hazards

• Aerosol considerations for chamber clearing


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.


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.


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


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.


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).


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.


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.


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


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)


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)


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


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)


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


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


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


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

, ,


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.)


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)


Est

imat

ed p

artic

le c

once

ntra

tion

for

hom

ogen

eous

nuc

leat

ion 1000 K

3500 K


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)


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)


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


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


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


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

idaho national engineering and environmental laboratory update on ife safety work for aries david...

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ife target manufacture

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