ryzhkov helium-3 2008

8/7/2019 Ryzhkov Helium-3 2008

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HELIUM-3 - BASED FUSION PLASMA

Sergei V. RyzhkovThermal Physics Department (E6)

Bauman Moscow State Technical UniversityMoscow, Russia

E-mail: [email protected]

SVR 2008

Alushta-2008 - International Conference and

School on Plasma Physics and Controlled Fusion

Alushta (Crimea), Ukraine, September 22-27, 2008

Sept. 26, Friday. Session X. 3-6
mailto:[email protected]:[email protected]


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Simple Cylindrical Configurations

Dont mix up with FRP, FRM and RFP !!!Astron is ring of relativistic electrons within a magnetic mirror device.ASTRON (the E-layer) never succeeded at achieving field reversal

FUSIONLAB in BMSTUhttp://fusionlabgroup.com/

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Mirror Trap

Prolate FRC

Oblate Spheromak

Advanced fuels

Open and Closed Systems by plasma confinement

and field lines
http://fusionlabgroup.com/http://fusionlabgroup.com/


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TABLE I. Experimental Plasma Parameters Ranges

Field ReversedConfiguration

Mirror Device Spheromak

Radius (orseparatrix), rs

0.02 0.40 m 0.02 0.40 m

0.25 12 m

1016 7.5 x 1022 m-3

0.03 10 keV

0.004 keV

0.005 15 T

12 70 %

0.01 1 ms

0.01 0.30 m

Length, ls 0.2 1.5 m 0.2 0.7 m

Electron density, ne 0.005 5 x 1021 m-3 0.001 1 x 1020 m-3

Ion temperature, Ti 0.05 3 keV 0.05 0.5 keV

Electrontemperature, Te

0.03 0.5 keV 0.02 0.5 keV

External B-field, Be 0.05 2 T 0.03 3 T

Average beta, 50 95 % 5 20 %

Energy confinement

time, E

0.05 0.5 ms 0.02 2 ms

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Alternative Experiments

J. Santarius, APS Meeting, 2006

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Main chamber 6 m long

http://www.aa.washington.edu/AERP/RPPL/programs/tcs.html

LSX: 2.5 m long FRTP chamber

2 m long translation section

TCSU: Ultra high vacuum

6 m long

Central cell 7 m longG. Fiksel, ICPP 2008 A.Anikeev, Zvenigorod 2008


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TABLE II. MF Experimental Devices (in alphabetical order)

FRC: Mirror: Spheromak:CBFR University of

California, Irvine, p-11BAMBAL-M - Budker

InstituteBCTX UC Berkeley,

heating of a decaying S

FIREX - Cornell U, Ithaca

MunsatUColorado,Boulder

CLM Columbia University BSX, CT injection, Caltech,

relevance to astrophys. jetsFIX Osaka University,

NUCTE-3 Nihon Univ.

GAMMA 10 Tandem MirrorPRC,University of Tsukuba

HIT-CT Himeji, Japan,CTIXUCDavis,acceleration

FRX-L LANL, MIF/MTF

compression, high density

GDT, SHIP BINP, LLNL,

tokamak refueling

HIT-SI U. Washington

new for form. S inductivelyKT, BN, TL, TOR TRINITI,

compression, translationGOL-3 Multiple Mirror Trap

Budker InstuteSPHEX UMIST, pf

structure, applied toroid field

Lebedev Physical Institute

RAS, Moscow

FLM - Uppsala Univ.; MAP-

II - Univ. of Tokyo, Hanyang

SSPX LLNL, high currents,

good confinementMRX Princeton, oblateflux-conserver, stability

HANBIT Device KoreaBasic Science Ins

SSSX, multi-probe surveysof the reconnection bet. 2 S

TCS, STX, TRAP, PHD, IPA

RMF, raise T, flux

MultiCusp Trap

Kurchatov Institute

TS-3,4 Tokyo, merging of

spheromaks, FRC, other TCFRM, Int. Coil Device, LD, LHD, LPD, RFP, rotomak, RT-1, TST-2, Z, -pinch

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Field Reversed Configurations:a) racetrack; b) Hills vortex/sphere, c) elongated

Non-uniform FRC equilibria

Open-filed lines (DEC)High (plasma/magnetic pressure)Poloidal magnetic field

1 2 3 4 5

0.2

0.4

0.6

0.8

1.0

-0.6 -0.4 -0.2 0.2 0.4 0.6

0.2

0.4

0.6

0.8

1.0

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Hills Vortex and Racetrack

B0 = 10 000; Bw = 10 000; rc = 150; rs = 100; L = 500; b = 400;

B0 = 8500; Bw = 8500; rc = 10; rs = 5; L = 50; b = 40 = 1.5

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Fusion Study Experiments


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Analytical Equilibrium for FRC

Sphere/ Hills vortex (HV) and Quasi-Equilibrium (SQE)

B is the nominal magnetic field, Be = Bc= B0 is the field at;

kand are small shaping parameters, and ~ 4/3.

( )UhU

zR

rBzrj c

2/

2

0

2

sec2

2),(

=UBzrB c tanh),( =

Uhpzrpm

2sec),( =

=

0

2

2

c

m

Bp

( )

2

1

sec),( Uhnp

pnzrn

m

m

m =

=

( )

( ) ( )

12

1

sec),(

=

= UhT

p

pTzrT m

m

m

( )

+

==

u

uuuU

1

1ln

2

tanh 1 ( )22/ 1 ududUU ==

( ) 122 = zRru ( ) ( )( )2144

0 21 sLzRzR =

constBBp c =

=

+

0

2

0

2

22

( )222

)/()/(12

bzarBr

HV =( )222

2

2

2zra

a

BrHV =

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Analytical Equilibrium for Elongated FRC

Solovev/ Hills vortex (EHV) and Steinhauer Quasi-Equilibrium (SAE)

( )2222

2

0

4

3 = ra

a

rBEHV

+=

2/322

32

0

)(1

2

r

arBEHV

ext

+

+=

2

2

2

2

2

2

12

2

0

2

0 42 a

z

a

r

a

rE

a

rE

aBSAE

ext

[ ] [ ]

+

+

++

++

2/1222/1222

)()( zbr

zb

zbr

zbE

)32/()4/)(1()4/)(6(1

11

2 6422

2

2

22

NNN

N

b

z

a

rBrSAE +++++

+

=

+

+

+

4

4

22

222

4

442

2

2

2

22422

2

3

841

4)

81(

21

4 b

z

ba

zr

a

r

b

z

a

r

where B0 is the external magnetic field, R2 =r2 +z2 , z/k,

k=b/a, =a/b, a=rs, b=ls. N is the shape index (1-EHV,0-RT)

[ ]22

1

2

2

5

12

)2(

34/

EE

EEaRbN s

++

+=

[ ]2/12

)/(1

1

+

=

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The FRC kinetic parameterS* is the ratio of the separatrix radius to the ion skin depth

S*/E< 3.5 ( 7-reactor). S* = rs/(c/pi) ~ rs/i. Elongation E=ls/rs, k Ls/rs

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FRC Operating Regimes

R. Siemon, ITC 2001, no RC

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The Spheromak has a q-profile,FRC Large Safety Factor

Typical Confinement Region in(r, P, E) space for racetrack

E is the total energy of a proton, P is its

canonical angular momentum. The separatrixradius rs=1 , and half length

ls=4 , external magnetic field Be=1 .

The most probable q profile (TCS) hassignificant magnetic sheardq/d, where is

the poloidal flux function.

The safety factor

The edge value of the safety factor

qedge 2.2First known instance of a very high-

plasma with a safety factor greater than 1.

The nominal stability is achieved if

g is the growth rate of the gravitational

mode in a FRC.

zBBEq

2~

0

1

=

=

rz

sedge

dr

dB

B

lq

= rBdlBq

z

21)(

2/)/(2/1

00 sgi lnmB >

Highly sheared flows are likely to play a

stabilizing role and possibly a transportreducing role.

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FRC Power BalanceThe global plasma power balance (the power losses are due to charged particle transport, neutrons,

and bremsstrahlung radiation) is given by, (1)

where Pf- fusion power, Pin - injection power, Pq - charged-particle transport power, Pn - neutronpower, Pb - bremsstrahlung power, and Pq - synchrotron radiation power. Power in units ofMW/m3, with Tin keV.

(2)

where and are the density of fuel ions, is the average reaction rate for reaction type i, and isthe fusion power of the reaction with , - charges of ion species i.

The charged particle transport power is evaluated,(3)

where is the FRC plasma volume, is the total ion density, is the ion temperature, is thedimensionless volume, and is the energy confinement time. This is the same as the thermal

energy divided by energy confinement time., (4)

where is the part of reacted tritium nuclei.The power per unit volume with relativistic correction due to bremsstrahlung (Bauman fusionlabgroup

formula) iswhere is the effective charge. , (6)

where Te, e and me are the electron temperature, charge and mass, respectively, and cis the speed oflight.

The synchrotron power is (Trubnikov's formula) to estimate the power loss due to synchrotronradiation in trap and compact torus.

(7)where rref is the reflection coefficient of the mirrors located at the plasma boundary, Cis the constant

for a layer, cylinder, or torus. For example, 9 10-29

for the tandem mirror and 4,1 10-17

for FRC. for plasma in both open systems (Mirror Trap and FRC) is summarized as:

f in q n b sP P P P P P+ = + + +

1 2

1 2( ),i i

z z

f i i fiP n n v E =

( ) /0032

i e e

qe

n T n T V duVP

+=

1

1

2

2 2

DD DT D D T n ff DD DT

n n nP v E v E = +

43 2 1/ 2 2 3 4 2 34.836 10 (1.1 0.59 3.06 2.56 0.85 ) 1.78 0.15 0.58 ,b e e eff P n T Z x x x x x x x = + + + + + 3 2=10 /( )e ex T e m c

5/ 2 1/ 2(1 )( ) ( ) ,e ref

s es

n rP C B T

r

=

3= + + + + + = const p T D eHe 3 . D fuelHeT T T const = = =

effZ

0V 0n iT/

V

e

1in 2in iv fE

1iz

2iz

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Bremsstrahlung Power

(Bauman FusionLabGroup formula)

0 50 100 150 200 250

0.0

0.2

0.4

0.6

0.8

1.0

1.2

TeHkeVL

Pb

HMWm

3L

0 50 100 150 200 2500

1

2

3

4

Rider

McNally

Svensson

Bauman

).58.015.078.1

)85.056.206.359.0

1.1(10836.4

32

432

2/1243

xxx

xxxx

ZTnp effeeb

++

+++

=

3 2=10 /( )e ex T e m c

Total (with corrections for dipole &quadrupole) radiation power in the

electrontemperature range 1-500 keV.

The impurity coefficient Z = 5/3, ne=2 1020 m-3

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TABLE D 3H T k k d FRC R tSVR 2008


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TABLE. D-3He Tokamak and FRC Reactors

Parameter Apollo ARIES-III ARTEMIS D-3He FRC

Electrical power 1000 MW 1000 1000 MW 1000

Fusion power 2144 MW 2682 1610 MW 1962

Bremss + Synchr. radiation 652+1027 MW Fraction0.72 357 MW 776+8.7

Neutron power 147 MW 110 77 MW 51.7

Injected (Current Dr.) power (138 MW) (172) 5 MW 62.6 MW

Net efficiency 0.43 Recirc. 0.24 0.36-0.62 0.49

Neutron wall load peak Aver. 0.1 MW/m2 Aver. 0.08 0.27 MW/m2 0.15

3He to D density ratio 0.63 ~ 1 0.5 1

Major (separatrix) radius 7.89 m 7.5 1.12 m 1.23Minor radius (separt. length) 2.5 m 2.5 17 m 30.75

Ion temperature 57 keV 55 87.5 keV 68.5

Electron density 1.9 x 1020 m-3 3.3 x 1020 6.6 x 1020 m-3 5.4 x 1020

Ion density 1.3 x 1020 m-3 2.1 x 1020 3.46 x 1020

TF on axis (external B-field) 10.9 (19.3) T 7.6 (6.7) T 6.38

Averaged beta 6.7 % Toroid. 24 % 90 % 74.8 %

Energy confinement time 16 s 11.8,p/E=2 2.1 s 1.44 s

Plasma current 53 MA 30 160 MA 298.8

Electron temperature 51 keV 53 87.5 keV 68.5

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Main Reactions:SVR 2008


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Main Reactions:D + T n (14.07 MeV) + 4He (3.52 MeV).D + D n (2.45 MeV) + 3He (0.82 MeV),D + D p (3.02 MeV) + T (1.01 MeV),

D + 3He p (14.68 MeV) + 4He (3.67 MeV).Aneutronic/ Low Radioactive Reactions:

3He + 3He 2p + 4He + 12.86 MeV.p + 6Li 4He + 3He + 4.018 MeV.

p + 11B 3 4He + 8.681 .3He + T D + 4He + 14.32 MeV. (3He + T n + p + 4He + 12.096 MeV)

6Li + 3He p + 2 4He + 16.878 MeV. (6Li + 3He n + p + 7Be - 2.112 MeV)D + 6Li 2 4He + 22.371 MeV. (D + 6Li n + 7Be + 3.381 MeV)

Fuel Cycle Radioactive fuel Direct radioactivity Indirect radioactiv

D-T T n n, T

D-D - n, T n

D-3He - - n, T

3

He -3

He - - -p-6Li - - n, T, 7Be, 11C

p-11B - - n, 14C

3H e - T T n n, T

6Li - 3He - n, 7Be n, T

D - 6Li - n, 7Be n, T

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Alternative Systems + Advanced Technology

Fig. . D-T and D-3He Design

Nonproliferation

Near term medical isotope production, cancer therapy,

FRC fueler for tokamak design (FFT), detection of explosives and chemical wastes.18O + p n + 18F; 94Mo + p n + 94mTc; 14N + p 4He + 11C;

16O + p 4He + 13N; 13C + p n + 13N; 15N + p n + 15O.

Mid term destruction of fissile material Long term small EPP plants, spaceand radioactive wastes. propulsion, hydrogen and synthetic fuel production.

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D-3He-6Li Fusion Cycleis a combination of conventional

(more deuterium) and aneutronic fuels:

). 2 stages reactor. The part of theD-3He fusion power going to support the

p-6Li reaction.Main reactions are shown

b). 1 reactor with D-3He-6Li mixture(assumed lunar helium-3)

c). Hybrid system (combination offirst and second schemes). Additional

reactions shown in the last box.

The auxiliary reactor:

1) Polarized beams

2) Catalyzed cycles

3) QSSPA

4) Reactor-breeder5) Colliding Beam Reactor

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Quasi-steady FRC Fusion Reactor

Fig. . PHDX and TCS-U in the University ofWashington (RPPL) andCompact Tori in the Lebedev Physical

Institute RAS

0,5 m diameter, 0,8 m length

0,1 m diameter, 2 m length

0,8 m diameter, 1,5 m length

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Transport in Compact Torus (CT)

Classical or Bohm or Anomalous?

Two-fluid effects Poloidal flows Two-fluid analysisNON-LINEAR WAVES IN SHEARED FLOWSNon-ideal effects, particularly finite Larmor radius

Distribution function f

(r,v,t) for -species of ash particles (p, , T) is described by

Fokker-Planck equation:

where the first term at the right hand of equation is the Fokker-Planck collisional operator;the second is the Boltzman collisional operator taking into account nuclear elasticinteractions; S

is the source of -species;

is the loss time. The last term is

modelling the ash removing.

( [ , ])a a a a

a

f f ez f v E v B

t r m v

+ + + =

a a aa

FP B a

f f f S

t t

= + +

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Particles Orbits MAGO

Fig.1. Proton (14.7 MeV) trajectory in (X-Y)space. Typical example for particle orbits inLAE with initial parameters B=1 T, x=y=0.4 m,

z=0, (theta)=90, (beta)=0.

MAGO (Russian abbreviation formagnetic implosion) in Russia andas MTF (Magnetized Target Fusion)in the United States is an alternativeto the main approaches (magneticconfinement systems and inertialconfinement fusion). Iskra 5,6

Uses a magnetic field within afusion plasma to suppress

thermal conduction.

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Applications of AFs and CTs

Thermonuclear Engine

Magnetic Fusion Rocket (MFR)

Proton/Neutron Source

Reactor

Thick Liquid Walled - Liquid LitiumLow recycling (wall pumping)

Resource ~ 50 y

Commercial Power Plant

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Conceptual Designs

Fig.. ITER, Artemis (D-3He FRC), and ARIES III (D-3He Tokamak)

R/a = 6.2 m/2 m, circumference 17 mDiameter 4 m, length 25 m

Plasma radius 1.12 m, length 17 m

Plasma major radius 7,5 m, minor radius 2,5 m

L. El-Guebaly, J.F. Santarius, ARIES Team. FTI, 2008.Advanced Research Innovation and Evaluation Study

H. Momota, NIFS, 1992.

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Inertial Electostatic Confinement (IEC)Steady-state D-3He proton production in an IEC fusion device

- ion source with low pressure

The first known non electrical application of

D-3He fusion energy the medical isotope of technetium

production, using molybdenum94Mo ( p , n ) 94mTc; 16O ( p , 4He ) 13N

S. Krupakar Murali, Ph.D. thesis 2004.

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Magneto Inertial Fusion (MIF)/Magnetized Target Fusion (MTF)

Plasma jet

Arrows indicate

flow direction

Plasma gun

Magnetized

target plasma

Plasma

liner

Stagnation Target Afterburner

point"

Radius(m) 0.00537 0.00943

n (1027 m-3) 6.0 5.9

T (keV) 10 0.02

B (T) 240 299

Merging Target Jets

radius"

Radius (m) 0.10 p=145 Mbar

n (m-3) 1024 initial 1024

Velocity 27 km/sT (keV) 0.002 0.001

B (T) 1 Energy req 100 MJ

These

parameters at

instant of impact

and at peak

compression for

DT-liner (Zn, Ar,

Xe pusher)

R i t/F

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Requirement/Fea

tureMFE MTF ICF

Starting density 1014 cm-3 1017cm-3 1021cm-3

Startingtemperature

20 keV 200 eV cyrogenic

Pulsed1000 seconds or

longer

Yes, a few

microseconds

Yes, a few

nanosecondsDriver

characteristics>150 MW, 25 MA,

(ITER)10 MJ, 50 MA

pulsed power1.8 MJ laser (NIF

class)

Cost of driver $10 Billion $50 Million $ 1.2 Billion

Fusion Yield ~0.5-1.5 GW ~ 20 MJ ~ 5 MJ

Magnetic fieldrequired

Yes,superconducting

yes no

Plasma wallinteractions

Yes, wall erosionis a problem

Mix of metal andplasma is bad

Rayleigh-Taylorlimitsconvergence

Plasma Beta < 1~1 to >> 1 ( the

plasma maylean on wall)

----

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Natural Gas Resources in East Siberia and Republic

Sakha (Yakutia) ~ 301012 m3 GazpromMain components, %

Gas field

Methane Nitrogen Helium Ethane 3-6

Kovykta (Kovyktinskoe) 91,39 1,52 0,28 4,91 1,78

Chayandinskoe 85,48 6,44 0,5 4,57 2,58

Yurubcheno-Tokhomskoe 81,11 6,39 0,18 7,31 5,06

Srednebotuobinskoe 88,61 2,93 0,2-0,6 4,95 3,12

Sobinsko-Paiginskoe 67,73 26,29 0,6 3,43 1,55V. Timoshilov, Oil & gas vertical 7, 2006.

Even % is a volume fraction, then for3He/4He = 0,710-6 1 m3 contains 0,005 0,710-6=0,3510-8 m3 of helium-3. Total 301012 3,510-9 = 105 m3 or 1,5104 kg, i.. ~ 15 tones!Just in Eastern Siberia! US + Algeria + Canada + Japan (Niigata bassin - 3He/4He higherratio) + China + Australia (reserve and resource)

Approximate power inputs on helium detachment (low temperature separation or producedrectification) from gases contained 0,02; 0,05; 0,5% He - 250, 100 and 10 kWh/m3.

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Terrestrial and Extraterrestrial Resources of3He

Sample Helium content

(volume x 10-6)

3He/4He(atom x10-6)

3He Potential(kg)

Atmosphere

Mantle gas vents

US natural gas wells:

Storage

RF natural gas reserves:

Storage

World resources

5,24

-

3000 (7 10-10 3He volume ratio)

106

~ 48 1012 m3

(3,5 10-9 volume ratio of3He)

~ 1014 m3 (3 1010 helium)

(g /g)

1,4 x 105 ion/m3

30 (20% of surface, 5mdepth)

7(80%of surface,10m d.)

2,2 3,5 x 105

2,2 3,5 x 105

1,4

11 21

0,2

0,2

~ 0,2 0,5

~ 0,1 0,3

4 x 106

3/year

187

29

~ 3500 (!!!)

~ 5500 (!)

Solar wind

Lunar surface:

Maria

Highlands

Jupiter

Saturn

480

400

400

140

140

3 107 ion/m2 s

6 x 108

5 x 108

7 x 1022

2 x 1022

Some numbers - Wittenberg L.J., Santarius J.F., Kulcinski G.L., Fusion Technology 10, 1986.

3He activitiesSVR 2008


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1st Lunar Development Symposium, Atlantic City, 22-24 September 1986GLK, JFS, LJW (KSW).1st Wisconsin Symposium on Helium-3 and Fusion Power, 21-22 August 1990, Madison.

US-USSR Workshop on D-3He Reactor Studies,25 September2 October 1991, Moscow.2nd Wisconsin Symposium on Helium-3 and Fusion Power, 19-21 July 1993, Madison.The Intern. Lunar Exploration Working Group (ILEWG) is a public forum created in 1994.9th International Conference on Exploration and Utilisation of the Moon (ICEUM9) held 22 - 26

October 2007 in Sorrento (2005 Toronto's Lunar Conf, ICEUM5 Hawaii 2003).

$1100/5l for3He, liquid 4He ~ $5/kg, gas 3He ~ 1,64M$/kg ($1,64 billion a ton), =134 g/m3

The abundance of helium on the Earth are estimated as 3x1010 m3. In the crust, the concentrationof He is in 200 bigger than in the atmos. RF total deep-laid gas - 48 x 1012 m3 (1680 1012 f3).East Siberia, Yakutia resources of natural gas - 301012m3 (helium-rich >0.5%).

Moon: ~ 500 million tones (regolith). Uranium:3

He/4

He = 1/3000, Jupiter: 1020

t (atmosphere),Saturn + asteroids + comets (asteroids more rich of helium-3).

3He-3He - 12,86 MeV (2,06x10-12 J). 1 gram ~ 2x1023 particles of helium-3. 1 ton of3He:12,86x106 x 1,6x10-19 x 2x1029 = 20,6x1016 J heat energy. I.. 1 t of3He ~ 5,4 million of oil!

D-3He - 18,36 MeV (3x10-12 J). 1 ton of3He: 18,36x106 x 1,6x10-19 x 2x1029 = 59x1016 Jthermal energy. I.. 1 t of3He ~ 15,5 millions of oil!

Oil - ~$150/bar. Urals (main russian brand) coefficient ~ 7,28 bar/t. 1 oil ton costs 1092$.At two billion dollars a t, the energy cost of3He is equivalent to oil at $7 per barrelWe can go up to $10-15 billion/t for Helium-3 from the Moon!

Even, for Wittenberg figures (7 x 10-10 for3He Volume Fraction in natural gas) we have:just for Siberia 30x1012 710-10 = 21103 m3 of3He 2,8103 kg, i.. 2,8 t (tones, not a few kg) !Irkutsk region (He reserve in 2025) ~ 30 106 m3. World: 27,8 109 1,4 10-6 x 0,134 = 5,2 t He-3 !!!

He activities


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D-3He Fusion Papers:

20. V.I. Khvesyuk, S.V. Ryzhkov, J.F. Santarius, G.A. Emmert, C.N. Nguyen, and L.C. Steinhauer, D-3He Field-Reversed Configuration Fusion Power Plants, Transactions of Fusion Technology 39, 410 (2001).

21. R.F. Post and J.F. Santarius, Open Confinement Systems and the D-3He Reaction, Fusion Technology, 22,13 (1992).

22. S.V. Ryzhkov, V.I. Khvesyuk, A.A. Ivanov. Progress in an alternate confinement system called a FRC,Fusion Science and Technology 43, 304 (2003).

23. S.G. Bespoludennov, V.I. Khripunov, V.I. Pistunovich, G.A. Emmert, J.F. Santarius, G.L. Kulcinski, D-3

HeTokamak - Reactor, Fourteenth International Conference on Plasma Physics and Controlled Nuclear FusionResearch, 30 September - 7 October 1992, Wrzburg, Germany (IAEA, Vienna, 1993), Peer-reviewed conference.

24. M.V. Krivosheev, V.N. Litunovsky, Compact D-3He fueled fusion reactor based on an FRC, Trans. of FusionTechnol. 27, 337 (1995).

25. F. Najmabadi, R. W. Conn, et al., "The ARIES-III Tokamak Fusion Reactor Study - The Final Report,UCLA report UCLA-PPG-1384 (1994). See http://aries.ucsd.edu/LIB/REPORT/ARIES-3/final.shtml.

26. W. Kernbichler, Operational parameters for D-3He in field-reversed configurations, Fusion Technol. 21, 2297(1992).

27. B. Coppi, P. Detragiache, S. Migliuolo, M. Nassi, B. Rogers, D-3He burning, second stability region, and theIgnitor experiment, Fusion Technol. 25, 353 (1994).

28. C.G. Bathke and the ARIES team, Systems analysis in support of the selection of the ARIES-RS designpoint, Fusion Eng. and Design 38, 59 (1997).

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CONCLUSIONS:

1. FRC viable high power density alternative to the tokamak

2. Advanced fuels such as p, D, and 11B are plentiful on Earth, but large

scale deployment of D-3

He power plants would require developing eitherbreeding or the large resource (~ 109 kg) on the lunar surface

3. JAEA, NASA, NASDA, Russian Space (Cosmos) Agency are seriouslyinvestigating the near term return of humans to the Moon, including theassessment and mining technology. Solar system exploration anddevelopment will be in progress, and lunar operations for science andpossibly 3He acquisition are likely to have begun. 3He acquisition requiresessentially developed technology

4. The importance of energy for the global environmental and theoretical

research program exists for the high beta configurations best suited toburning advanced fusion fuels

5. As such, they deserve further study, but the present worldwide budget foradvanced fuel research is less than $1M...

ryzhkov helium-3 2008

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