4 - History of Direct Charge Nuclear...

35
Radioisotope Batteries Jake Blanchard University of Wisconsin April 2010

Transcript of 4 - History of Direct Charge Nuclear...

Page 1: 4 - History of Direct Charge Nuclear Batterieshomepages.cae.wisc.edu/~blanchar/res/SDBatteryTalk.pdf · Introduction Radioisotope batteries provide reliable batteries with high energy

Radioisotope Batteries

Jake Blanchard

University of Wisconsin

April 2010

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Introduction

Radioisotope batteries provide reliable batteries with high energy density

They are valuable when long life is needed and recharging or refueling is difficult

Many of the conversion technologies can function in harsh environments

They can be very useful as onboard MEMS power sources

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Applications

Long-lived cell phone batteries

Self-powered sensors on automobiles

Self-powered sensors in humans

Sensors for tracking animals

Building/bridge sensors

MEMS

Micro-robots

Smart Dust Networks

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Caveats

Cost

Safety/regulation

◦ Shielding is generally simple

◦ Concern is with breakage of packaging

◦ Security is also an issue

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Radioisotopes

Alpha emitters – release energetic He

nuclei – typically at 4-6 MeV per particle

Beta emitters – emit electrons or

positrons (and neutrinos or

antineutrinos) – energy spectrum

Gamma emitters – emit electromagnetic

radiation – penetrating - undesirable

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Isotope Selection

Type of radiation◦ Alpha

◦ Beta

Half-Life◦ Long - Long battery life (238-Pu – 0.6 W/g, 86 yr half life)

◦ Short - Higher power density (210-Po – 137 W/g, 3 month half-life)

Avoid gammas in the decay chain (safety)

Watch out for (alpha, n) reactions and Brehmstrahlung

Watch particle range, displacement damage, and cost

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Radioisotopes and decay

Isotope Average energy

Half life

Specific activity

Specific Power

Power Density

(KeV) (year) (Ci/g) (W/g) (W/cc)

63-Ni 17 100 57 0.0067 0.056

3-H

5.7 12 9700 0.33 -

90-Sr/ 90-Y

200/930 29/2 d 140 0.98 2.5

210-Po

5300 0.38 4500 140 1300

238-Pu 5500 88 17 0.56 11

244-Cm 5810 18 81 2.8 38

M

NX

M

NX

M-1N

Y

e- ne

M-2N-4

Y

2

4Hea-decay b-decay

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Beta Spectra (E in MeV)

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What is a Nuclear Battery?

Goal: convert energy from radioactive

decay to electricity

Options:

◦ Direct charge collection

◦ Indirect (scintillation)

◦ Betavoltaic

◦ Thermoelectric

◦ Thermionic

◦ thermophotovoltaic

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Comparison

Consider 1 mg for power source

Source Energy Content (mW-hr)

Chemical Battery (Li-ion) 0.3

Fuel Cell (methanol, 50%) 3

210-Po (5% - 4 years) 3000

3-H (5% - 4 years) 500

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Direct conversion nuclear battery: collecting charges emitted from radioisotopes with a capacitor to achieve high voltage output(J. H. Coleman, 1953)

Direct conversion nuclear battery

High voltage

Radioisotope

Collector

C

QV

10-100 kV voltages can be

created in vacuum

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Static Accumulation

Linder, Rappaport, Loferski

•Early 1950’s

•Source at K

•D is electrical insulator

•Chamber is evacuated

•0.25 Ci Sr-90

•365 kV

•About 1 nA

•0.2 mW

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Adding a Dielectric

Keller et al

•Early 1950’s

•Source at S

•D is dielectric; C is collector

•Radiation penetrates dielectric

•No need for vacuum

•High voltage

•Prevents secondary electrons from

getting back to source

•50 mCi Sr-90

•polystyrene

•7 kV

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Secondary Collector

Shorr

•Use beta source

•MgO used to maximize

secondary’s

•Collector is graphite

coated Al

•1e-5 mm Hg vacuum

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Contact Potential

Ionize gas between two plates

Dissimilar plates will develop

potential due to differing work

functions

Low efficiency (low absorption

coefficient) and high ionization

energy (30 eV)

Operates at 1-2 V

Shorr

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Pacemakers

3 Ci Pu-238

~3 ounces, ~3 inches

<mW power levels

100 mrem/y to patient

Since supplanted by Li batteries (~10 yr life)

Regulators nervous about tracking Pu

Thermoelectric (some betacell concepts)

http://www.naspe.org/library/electricity_and_the_heart/

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Radioisotope Thermoelectric

Generators (RTGs)

Used in many NASA

missions

Use radoisotope (usually

ceramic Pu-238) to

provide heat

Electricity produced by

thermoelectric

No moving parts

41 have been flown by

US

• Fuel: 2.7 kg. 133 kCi

• Power: 276 W

• Power (11 years): 216 W

• Total Weight: 56 kg

• Lifetime: over 20 years

• Dimensions: D=42 cm,

L=114 cm

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Heating Units

NASA’s RHU

33 Ci

Power is 1 W

1.4 oz.

1 cubic inch

2.7 g of Pu-238 (oxide form)

Rugged, reliable

http://nuclear.gov/space/rhu-fact.html

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A Compact Thermoelectric

John H. Glenn Research Center, Cleveland, Ohio

Hi-Z Technology and JPL

40 mW electric power

240 cm3, 300 g total weight

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Betavoltaic Microbattereis

• First type: planar Si pn-diode with electroplated 63Ni

PN-diode

DIP

packageLeads Glass

Electroplated 63Ni thin film

-3

-2.5

-2

-1.5

-1

-0.5

0

0 50 100 150

Cu

rren

t (n

A)

Voltage (mV)

• Second type: inverted pyramid array Si pn-diode

0.25mCi 1mCi

0.71nA 2.41nA

64mW 115mV

0.04nW 0.24nW

IpVoc

Pmax

- Nanopower( 0.04~0.24nW) obtained/ - No performance degradation after 1 year

63NiCl/HCI solution

PN

Glass

(8Ci/l)

- Area magnification: 1.85 / - 0.32nW (128mV/2.86nA) obtained

• Efficiency:0.03~0.1% ~10 times > micromachined RTG

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Scaling of Power

Currently 1mCi of 63Ni is used◦ Source density of~0.0625 mCi/mm2 leads to

2~8 nW/cm2

10mCi~100mCi of 63Ni is expected to be used◦ Source density is ~1~2 mCi/mm2

◦ 100nW ~200 nW can be obtained

◦ Gives 100~200 nW/cm2

Energy conversion efficiency of 0.5~1% is expected to be achieved◦ Theoretical conversion efficiency: 3~5%

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Using Radioisotope 147Pm

• Another way to raise power output : using high energy power source

- 147Pm, with Eavg= 62 keV and Emax= 220 keV and half-life of 2.6 year is also

a promising pure beta source for microbattery.

• Preliminary Results

NP

147Pm

SiO2

-1m of SiO2 is used as protection layer

- Device area : 2mm 3mm

- 5mCi of 147Pm is used

- test result : Is= 140nA, Voc=183mV, Pmax = 16.8nW

- Conversion efficiency: 0.62%

- long-term stability is under test

-1.E-07

-8.E-08

-4.E-08

-1.E-23

0.00 0.05 0.10 0.15 0.20

Cu

rren

t (A

)

Voltage (V)

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Porous Silicon

Try to maximize area exposed to source

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Thin, Flexible Semiconductors

For low energy beta emitters, source

layers must be thin (sub-micron)

Range of particles in semiconductor is

also a few microns at most

Hence, thin semiconductors are an

advantage

Multi-layer devices can offer good power

density with good efficiency

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Self-Absorption – Ni-63 and Si

0.3

0.4

0.5

0.6

0.7

0.8

0.9

1

0 0.2 0.4 0.6 0.8 1 1.2

2-s

ided

esc

ap

e p

rob

ab

ilit

y

source thickness (microns)

MCNP (no diode)

MCNP (with diode)

chord method

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Silicon Carbide

Wide Bandgap semiconductors offer

hope for larger efficiencies

Simulations indicate on the order of 25%

conversion efficiency

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A “New” Concept

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Self reciprocating cantilever

0 2 4 60

10

20

30

Time (minute)

Dis

tan

ce (m

)

Experimental dataCalculated values

Initial gap (d0): 33 m

Period: 6 min. 8 sec.

Residual charges: 2.310-11C

Peak force (kd0): 10.1 N

Assumed Collection efficiency (a): 10%

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Self-reciprocating SiN cantilever

The cantilever is made of low stress SiN thin film with dimensions 500 m 300 m 1.7 m .

The cantilever is mounted on a DIP package for wire bonding.

Four poly resistors form a Wheatstone bridge to measure the deflection of the cantilever.

The signal from the Wheatstone bridge is sent to an instrumentation amplifier and then output from the amplifier is measured.

0 5 10 15 20 25 30 350

0.2

0.4

0.6

0.8

1

1.2

Time (s)

Dis

tan

ce (

m)

Blue: measured deflectionRed: signal from the Wheatstone bridge

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Self-powered

Sensor/Actuator/Transmitter

-0.5 0 0.5 1 1.5 2 2.5

-0.2

-0.1

0

0.1

0.2

0.3

Time (s)

Vo

ltag

e (

V)

(a) (b)

C1

C2

C3

To oscilloscope Nickel-63 source

PZT

Au electrodes

C1

C2

C3 C4

ε

To oscilloscope

Nickel-63 source

PZT

dt

dVCI 1

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Bottom Line

Market is applications which can justify

cost and risk of using radioisotope fuels

Advantage is very long life

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Comparing Technologies