Transcript The perspective of fusion and fission power plans

Researches and applied measurements on
nuclear physics and atomic power plants
fields
in the Institute of Isotopes
Árpád VERES
Scientific advisor
Institute of Isotopes of HAS 1525 Bp. Pf. 77
e-mail: [email protected]
6-10-2009, Hanoi, Vietnam
Contents of lecture
• Research Departments of Institute of Isotopes.
• Nuclear isomers and its applications.
• Present state of nuclear fission power plants.
(Comparison of IKI-measurements and Pakscalculations for burn up of fuel assembles). The
electricity and the nuclear wastes produced by critical
power plants.
• Accelerator-Driven (spallation), subcritical nuclear
fission power plants.
• Nuclear fusion power plants.
6-10-2009, Hanoi, Vietnam
Departments of the Institute and its research areas:
Radiation Chemistry: Radiation and photochemistry of hydrocarbons;
Degradation of environmental pollutants e.g. chlorinated aromatic
hydrocarbons, reactive textile dyes; Polymer radiation chemistry and
mechanism of radiation induced polymerization; Radiation methods for
synthesis of polymers for biomedical applications.
Surface Chemistry and Catalysis: Studies on surface of highly dispersed
metal particles. Structure, catalytic effect of carbonaceous deposits
formed during refinery model reactions; Study the selective oxidation of
CO (PROX) in presence of hydrogen for fuel cell application; Study of
surface species formed on platinum upon chemisorption of low
molecular weight hydrocarbons applying Auger spectroscopy.
Radionuclide Applications: Identification of various oxidation and
coordination states in iron or tin containing catalysts by in situ
Mössbauer spectroscopy. Study of radioisotope migration typical of
high-level nuclear waste in geological samples (borecores).
6-10-2009, Hanoi, Vietnam
Nuclear Research Department
•Prompt Gamma Activation Analysis (PGAA)
and its applications.
•Nuclear spectroscopy with neutron-induced
reactions.
• Nuclear data measurements and evaluation.
Gamma-ray spectrometry and metrology.
•In-beam Mössbauer spectroscopy.
Research Reactor
20 MW, water cooled, water moderate, thermal flux 1014 cm-2 s-1
6-10-2009, Hanoi, Vietnam
Radiation Safety Department
• Dosimetry section: Chemical dosimetry; Solid state
dosimetry; environmental, accidental, reactor and
personal dosimetry; Radiation processing
dosimetry; Dosimetry control at high-activity
gamma and at high-energy electron irradiation
facilities; Radiation protection services
• Radioactive Material Registry Section: Center
registry of radioactive materials in Hungary;
Software development for the central registry.
• ICP-MS Mass Spectrometry Laboratory
• Nuclear section
6-10-2009, Hanoi, Vietnam
Inductively Coupled Plasma Mass Spectrometry
(ICP-MS)-IAEA secondary standard laboratory
•
•
•
•
•
•
•
Environmental samples
Samples in connection with
radiation protection
Safeguards samples
Confiscated samples (illicit
trafficking)
Samples from the field of Nuclear
Physics
Investigation of catalysts
Food samples for authenticity
studies
6-10-2009, Hanoi, Vietnam
Nuclear section: Nuclear safeguards; Combating illicit trafficking of
nuclear materials; Photo excitation; Reactor
Spent Fuel Attribute Tester
at Paks Power Plan
(SFAT)
Safeguards measurements
of the damaged,re-encapsulated fuel
at Paks Power Plan
6-10-2009, Hanoi, Vietnam
Nuclear section:
Age determination of Uranium sample
by gamma-spectrometry
234U
230Th
226Ra
222Rd
Low-background iron chamber (20 cm wall thickness) with coaxial
HPGe detector Large area (~20 cm2) planar HPGe detector
Other laboratories
(mass-spectrometry)
Our laboratory
(gammaspectrometry)
22.2 - 22.6 years
22.4  1.2 years
23.5  0.5 years
23  3 years
6-10-2009, Hanoi, Vietnam
Clock: 214Bi/234U
218Po
214Pb
214Bi
Nuclear section:
Identification Neutron Sources
by neutron coincidence technique: R/T-T method
Neutron coincidence counting:
•
•
3He
tubes around the source +
shift register or pulse train register
• Total neutron count, T
• Coincidence neutrons, R, from
–
–
–
Moderator
Neutron detectors
(3He tubes)
source
holder
6-10-2009, Hanoi, Vietnam
n-induced fission inside sources
9Be(n, 2n)8Be reaction
spontaneous fission
Nuclear section:
PHOTO EXCITATION
6-10-2009, Hanoi, Vietnam
Short chronology of nuclear isomers
•1921. Otto Hahn observed the isomeric state of
decay of 234Th
234Pa
from the -
•1935. V. Kurcsatov et al. produced 80Brm by (n,) reaction
•1936. C. F. Weizsäcker recognized that the nuclear isomerism may
occur whenever the angular momentum of a low-lying state of
nucleus differs from the angular momentum of any lower state by
several units of h/2.
•1938. M. Goldhaber, R. D. Hill, L. Szilard reported conclusive
evidence of nuclear isomerism in a stable nucleus. They found that
the 4.1 hour - activity of indium could be product by fast neutron
6-10-2009, Hanoi, Vietnam
•1939. Pontecorvo et al. observed isomeric state of stable 115In
nuclear by x-ray excitation.
•1939. M. Goldhaber et al. irradiated indium target with the -rays
emitted by 0.5 g 226Ra to obtain isomeric activity by the
115In(,’)115Inm reaction. Negative results.
•1954. G. Harbottle estimated the activity of 6oCo and of 182Ta γsources from the measured isomeric number of 115In(γ,γ’)115Inm
reactions.
•1956. N. Ikeda, K. Yoshihara measured the cross section (σexp) of
111Cdm and 115Inm by 60Co γ-source.
•1963. Á. Veres also measured the cross section of isomeric state of
ten stable nuclei (77Sem, 87Srm, 89Ym, 107,109Agm, 111Cdm, 115Inm, 179Hfm,
191Irm, 195Ptm, 197Aum, and 199Hgm) by gamma rays of 60Co and
estimated its partial level width of activation levels (~1.1 MeV) too.
There where between in the range of 10-4-10-7 eV.
6-10-2009, Hanoi, Vietnam
5-09-1962. One of the first measurements of photoactivation
of isomers by γ-rays of 60Co. (L. Szirtes, Á. Veres, P. Bedrossián)
6-10-2009, Hanoi, Vietnam
Ea
Irradiation facility
Em
Eg
The ↻ shows the irradiation and store
position of the source.
The ↥ shows the install the target in
irradiation position.
1.
Target nuclei which are excited
by γ-rays to the isomeric state.
2.
60Co source (1.3 kCi ~ 48 TBq)
3.
Lead container (shielding 2.2
tons)
6-10-2009, Hanoi, Vietnam
Chart of the isomers of stable nuclei
N
43
Z
34
77Sem
44
47
49
50
52
56
58
60
62
107Agm
109Agm
44.3 s
39.6 s
63
64
65
17.4 s
79Brm
35
4.9 s
83Krm
36
1.83 h
87Srm
38
2.8 h
89Ym
39
16 s
90Zrm
40
0.8 s
93Nbm
41
16.1 y
99Tcm
43
6.01 h
103Rhm
45
56 m
47
48
6-10-2009, Hanoi, Vietnam
111Cdm
111Cdm
48 m
48 m
N
Z
49
63
65
113Inm
115Inm
1.7 h
4.5 h
50
67
69
117Snm
119Snm
71
73
75
77
79
80
81
99
106
13.6 d 293 d
52
123Tem
125Tem
120 d
57.4 d
54
120Xem
131Xem
8.9 d
12 d
135Bam
56
136Ba
28.7 h 0.3 s
137Bam
2.6 m
167Erm
68
2.6 m
176Ybm
11.4 s
70
N
Z
71
72
105
176Lum
3.64 h
106
107
108
177Hfm2
178Hfm2
179Hfm1
180Hfm
51 m
31 y
18.7 s
5.5 h
N
Z
74
109
183Wm
5.2 s
76
113
114
116
189Osm
190Osm
192Osm
5.8 h
10 m
191Irm
4.9 s
6.1 s
193Irm
10 d
125
207Pbm
0.8 s
127
143
180Tam
73
N
Z
78
117
195Ptm
4.02 d
118
1.2 Py
77
119
N
Z
82
210Bim
197Aum
79
7.73 s
83
43 m,
3 My
235Um
199Hgm
80
122
204Pbm
67 m
92
25 m
6-10-2009, Hanoi, Vietnam
The codes of colors
1 sec to 1 hour: 20
isomers
1 hour to 1 day: 10
isomers
1 day to 1 year : 8
isomers
 1 year: 5
isomers
scarlet
Yellow
green
blue
It was brought up the question
in the literature, that whether
the mechanism of the isomeric
activation has non resonant
character or not.
Photo excitation in next years
IDEA OF NON-RESONANT PROCESS
(primary gamma 662 keV directly excitation
isomers)
•
•
In this situation, in 1981, during the studies of (,’)
reaction being basis on the resonance fluorescence,
Ljubicic, Pisk, and Logan [1] suggested that the
nonresonant-type process might be dominant in
nuclear photoactivation of 115In by 60Co source
A technique was give for distinguishing between
resonance and non-resonant process
Integral cross section of 115In by 60Co excitation
6-10-2009, Hanoi, Vietnam
NO-RESONANT and RESONANT
[1] A. Ljubicic, K. Pisk, and B. A. Logan, Phys. Rev. C 23, 2238 (1981).
[2] M. Krcmar, A. Ljubicic, K. Pisk, B. A. Logan, and M. Vrtar, Phys. Rev. C 25, 2097 (1982).
[3] M. Krcmar, A. Ljubicic, B. A. Logan, and M. Bistrovic, Phys. Rev. C 33, 293 (1986).
[4] K. Yoshihara, Zs. Nemeth, L. Lakosi, I. Pavlicsek, and A. Veres, Phys. Rev. C 33, 728 (1986).
[5]I. Bikit, J. Slivka, I. Anicin, L. Marinkov, A. Rudic, and W. D. Hamilton, Universitet Novi Sad Report 17. Physics
Seriet (1987).
[6] I. Bikit, J. Slivka, I. Anicin, L. Marinkov, A. Rudic, and W. D. Hamilton, Phys. Rev. C 35, 1943 (1987).
[7] J. A. Anderson, M. J. Byrd, and C. B. Collins, Phys. Rev. C 38, 2838 (1988).
[8] P. vonNeumann-Cosel, A. Richter, J. J. Carroll and C. B. Collins Phys. Rev. C14, 554 (1991).
[9] M. Krcmar, S. Cancic, T. Tustonic, A. Ljubicic, B. A. Logan, and M. Bistrovic, Phys. Rev. C 41, 771 (1990).
[10] M. Krcmar, A. Ljubicic, B. A. Logan, and M. Bistrovic, Phys. Rev. C 47, 906 (1993).
[11] T. Tustonic, ] M. Krcmar, A. Ljubicic and M. Bistrovic, Appl. Radiat. Isot. 48, 45 (1997).
[12] D. A. Bradby, Ithnin Abdul Jalil, M. Krcmar, and A. Ljubicic, Journal of Radianalytical and Nuclear Chemistry
244, 475 (2000).
[13] Chea-Beng Lee, D. A. Bradley, Ithnin Abdul Jalil, Y. M. Amin, Mohd Jamil Maah, Khairul Zaman M. Dahlan,
Radiat. Phys. Chem. 61, 367 (2001).
[14] K. Pisk, M. Krcmar, A. Ljubicic, and B. A. Logan, Phys. Rev. C 25, 2226 (1982).
[15] M. Krcmar, A. Ljubicic, and K. Pisk, FZKAAA 18, 171 (1986).
[16] Ljubicic, Radiat. Phys. Chem. 51, 341 (1998).
[17] Drukarev. 2000. No-resonant excitation of nuclear levels by photon. In: R. W.Dunford, D. S . Gemmel, E. B.
Kanter, B. Krassig, S. H. Southworth, L. Young, (Eds), X-rays and Inner Sell Processes, 18 th International
Conference, Chicago, IL, August, AIP Conference Proceedings 506, American Institute of Physics, Melville, NY,
pp. 496-500
6-10-2009, Hanoi, Vietnam
Explain in other way
without using the non-resonant process
Compton effect in shielding-, absorbermaterial and in target on Resonant flux
6-10-2009, Hanoi, Vietnam
Nuclear Power Plants
Fission Power Plants
Fusion Power Plants
6-10-2009, Hanoi, Vietnam
The present state and perspectives of fission and
fusion power plants
(Types of the nuclear power plants)
I. Nuclear fission power plants:
I.1. Critical reactor convert energy released from the nucleus
of an atom, mainly via of 235U.
I.2. Accelerator-driven subcritical reactors used by
transmutation of nuclear wastes as fuel.
II. Nuclear fusion power plants use the fusion of
deuterium and tritium as fuel.
II.1. Magnetic confinement . Tokamak-driven.
II.2. Inertial confinement. Laser-driven.
6-10-2009, Hanoi, Vietnam
I.1. The first n-pile and nuclear power plant
December 2, 1942. Nuclear
reactor Chicago-Pile-1. USA.
(Led by Enrico Fermi, the
idea of Leo Szilard).
June 27, 1954. Nuclear Power
Plant, USSR, Obninsk. It
produced 5 MW electric
power.
6-10-2009, Hanoi, Vietnam
The critical power plants
1. Generation I. Early prototype reactors, i.) 1954, the first nuclear
power plant (5 MW) Obninsk, USSR; ii.) 1956, Calder Hall in Sell
afield, England a gas-cooled Magnox reactor (50 MW, later 200
MW); iii.) 1957, the Shipping port Reactor (Pennsylvania, USA),
pressurized water reactor.
2. Generation II. Commercial reactors 1965-95 (more than 400), LWRPWR, BWR, CANDU, WWR/RBMK. (4 VVR-440 units of Paks,
Hungary was installed between 1982-87)* The next 8 slides.
3. Generation III. 1995-2010 Temperature Advanced LWRs, System
80+, AP600, EPR. Gen. III+ 2010-2020 Improved economist.
4. Generation IV. Very High Temperature Reactor (VHTR) called Next
Generation Nuclear Plant (NGNP). Completed 2021. Primary goals:
improve nuclear safety, proliferation resistance, and to minimize
the nuclear wastes.
6-10-2009, Hanoi, Vietnam
*Earlier achievements in Paks (Hungary)
•Total safety evaluation of the units was accomplished in 1994.
•An efficiency enhancement due to reconstruction of the secondary loop
and replacements of the turbines increased the original 440 MW of
electric power to 470 MW. The total 1790 MW is about 40 % of the
Country electricity.
•Between 1996 and 2002 the costs of the Programme of Safety
Measurements (PSM) amounted to 60 billion Fts. (~ 300 M$). The average
sale price of the Paks NPP was 10.16 Ft/kWh in 2008.
•The specific costs of generation of the extra-power, the investment cost of
the extra-capacity enhancement was shown to be the lowest as compared
to the cost of building new different type power plants.
Power plant
Specific investment costs [bFt/MW]
New lignite
350
New gas turbine
125
Biomass
400
Capacity upgrading of Paks NPP
~40
6-10-2009, Hanoi, Vietnam
Nuclear section:
COMPARISION OF IKI-MEASUREMENTS
AND PAKS-CALCULATION FOR BURNUP OF FUEL
4 block of Paks Nuclear Power plant, Hungary
6-10-2009, Hanoi, Vietnam
STRUCTURE OF ONE BLOCK
VVER-440 REACTOR
6-10-2009, Hanoi, Vietnam
STRUCTURE OF VVER-440 REACTOR
REACTOR CORE
6-10-2009, Hanoi, Vietnam
C-PORCA BURNUP-CALCULATION
FOR EVERY 126-RODS OF ALL-ASSEMBLIESS
48 Nodes
126 Rods
FUEL ASSAMBLE
6-10-2009, Hanoi, Vietnam
IKI- BURNUP-MEASUREMENTS
MEASUREMENTAL SET UP
Spent fuel assemble
Fission Chamber + Si diode detector
HP-Ge detector
Collimator
CZT detector
6-10-2009, Hanoi, Vietnam
A TYPICAL GAMMA SPECTRUM
MEASURED BY HP-GERMANIUM DETECTOR
Ru-Rh106
622 keV
Cs134
604,7 keV
Cs137
661.7 keV
Cs134
795.8 eV
Ru-Rh106
1050 keV
Ru-Rh106
1128 keV
Ru-Rh106
512 keV
1000
Cs134
802 keV
Cs134
1168 keV
Eu154
1274 keV
(a)
(c)
Cs134
1366 keV
(b)
Couts
(e)
(a): Ce-Pr144
696.6 keV
100
Ce-Pr144
1489 keV
(d)
(b): Eu154
723 keV
(c): Eu154
873 keV
(d): Eu154
1005 keV
(e): Cs134
1039 keV
10
0
500
1000
Energy (keV)
6-10-2009, Hanoi, Vietnam
1500
2000
THE RESULT OF 56993-ASSEMBLE
56993 Axial frofile
56993 3.bl. 4. Radius profile
0,7
20
10
10
50
0,6
Cs134/Cs137
Cs137
20
BU calculation
30
Mear.Cps
számolt
40
0,5
0,4
30
0,3
20
0,2
326
350
cal..
10
0,1
0
0
1700 2200 2700 3200 3700 4200 4700
BU calculation
30
0
-180
-120
Vertical position
-60
0
60
120
0
180
szög
24.pozíció él
1
40
30
6
2
20
10
0
5
3
4
Comparison
6-10-2009, Hanoi, Vietnam
EXPECTED APPLYCATION
OF THE IKI-TECHNIQUE
•Control the Burnup
calculation
•Studying the asymmetry of
the Reactor
•Problems of security of the
Reactor.
•Control yield of some fission
production
The electricity and the nuclear wastes produced by
critical power plants
1. In 2007 operated 440 power plants in 32 countries of the
world and produced 370 GW-year (~2.6×1012 kWh). This
is about 16 % of the world's electricity.
2. If we assume the above level of global nuclear power
generation, then in the year 2015 there will be more
then 250 000 tons of spent fuels worldwide, containing
over 2000 tons of weapons-usable Pu. Over 70 000 tons
of this spent fuel (<500 t of Pu) will be in the USA, > 1/3
in Russia and < 1/3 in Europe and others.
6-10-2009, Hanoi, Vietnam
The amount of TrU and fission products in 1 ton
spent fuel (33 MWd/kg) [g/t]
TrU
T1/2 (y) [g/t]
239Pu
24 400 5450*
237Np 2 100 000 450
243Am
7 400 100
245Cm
8 500
1,2
Fp.
T1/2 (y)
99Tc
210 000 810
135Cs
129I
[g/t]
2 300 000 360
16 000 000 170
* Total: Pu : 9 700
The problem: Nuclear waste from commercial power plants
contains large quantities of Pu, other fissionable actinides, and
long-lived fission product that create challenges for storage and
that are potential hazardous proliferation concerns.
6-10-2009, Hanoi, Vietnam
I.2. Accelerator-Driven (spallation), subcritical power plants
The spallation is a high-energy nuclear reaction in which a target
nucleus struck by an incident particle of energy (usually < 500 MeV)
ejects numerous lighter particles and becomes a product nucleus
correspondingly lighter than the original nucleus.
6-10-2009, Hanoi, Vietnam
50
40
Secund neutrons (n/GeV)
The neutron-yields
of heavy elements
(U, W, Pb) produced
by 0.5-5 GeV proton
energy [Y = 18-45
neutrons per
proton].
45
35
30
25
20
U-238
15
W
10
Pb
5
0
0
0,5
1
1,5
2
2,5
Protonenergy (GeV)
3
3,5
4
4,5
5
The accelerator can drive 2×500 MWe power plants by transmutation
of 400 kg/year of 239Pu and 100 kg/year of other fissionable actinides.
6-10-2009, Hanoi, Vietnam
A block diagram of accelerator and ATW configuration
6-10-2009, Hanoi, Vietnam
USA concept for the transmutation of spent fuel nuclear wastes.
Beller et al, Nucl. Instr. Meth. A463, 468, (2001)
On 2036 year the amount of spent fuels will be: > 86 000 ton, in
which the most problematic fission products are the 99Tc (93 t) and
the 129I (20 t).
The ATW systems could be used in a series of different scenarios.
6-10-2009, Hanoi, Vietnam
Time schedule and milestones for the development of an accelerator
driven systems (ADS) and accelerator driven transmutation (ADT)
technology in Europe
6-10-2009, Hanoi, Vietnam
Some Accelerator-Driven programs for
Transmutations of nuclear wastes
•1987. CERN, JRC (Dubna), BNL (13-28 MeV proton-cyclotrone, TRU
target/fuel, 900 MWt
•1989. JAERI (Japan) OMEGA project salt-solution target
•1990. BNL PHOENIX project, 1,6 GeV-104 mA p-linac
•1991. LANL ATW, 1016 n/cm2s, 100-180 MeV p-linac, actinide fuel.
•1993. CERN (Rubbia), 0,8 GeV-6,25 mA accelerator as driver for a
power reactor a target with thorium as fuel and lead as a coolant.
•1996. Belgium, MYRHA project, 250 MeV-2 mA proton-cyclotrone. n
~1,5×1015 n/cm2, the volume of zone: 35 cm3
•Many institute of 12 Countries co-operate in 20 project.
6-10-2009, Hanoi, Vietnam
FUSION POWER PLANTS
II. Nuclear fusion power plants
Magnetic Fusion Energy (MFE). Inertial Fusion Energy (IFE).
Fusion is the joining
together of small, light
nuclei to form a larger,
more massive nucleus (the
deuterium-tritium is the
most popular reaction, but
there are others).
The problem is that combination of high temperatures and densities
are required to force positively charged nuclei together, but the
resulting high pressure will tend to blow fusion plasma (hot ionized
gas) apart.
6-10-2009, Hanoi, Vietnam
Fusion Methods: 3 primary plasma confinement.
i.Magnetic confinement;
ii. Gravitational confinement -- astrophysical contexts;
iii.Inertial confinement -- inertia of the fuel confines it for the nanoseconds
(10-9 s) required for the fusion reaction to proceed.
Difference between magnetic- and inertial confinement:
1. In magnetic confinement, the tendency of the hot plasma to expand is
counteracted by the Lorenz force between currents in the plasma and
magnetic fields produced by external coils. The particle densities tend to
be in the range of 1018 to 1022 m-3 and the linear dimensions in the range
of 0.1 to 10 m.
2. In contrast, with inertial confinement, there is nothing to counteract the
expansion of the plasma. The confinement time is simply the time it
takes the plasma pressure to overcome the inertia of the particles, hence
the name. The densities tend to be in the range of 1031 to 1033 m-3 and
the plasma radius in the range of 1 to 100 micrometers.
6-10-2009, Hanoi, Vietnam
Types of fusion
Methods of fusing nuclei
Magnetic
confinement
Tokamak – Spheromack – Stellator – Reversed fiel pinch – FieldRevised Configuration – Leviated Dipole
Inertial
confinement
Laser driven – Z-pinch – Bubble fusion (acoustic confinement) –
Fusor (electrical confinement)
Other forms of
fusion
Muon-catalised fusion – Pyroelectric fosion – Mignon – Polywell –
Dense pasma focus
Devices
List of fusion experiments
Magnetic
confinement
devices (20)
ITER (International) | JET (European) | JT-60 | Large Helical Device
(Japan) | KSTAK (Korea) | EAST (China) | T-15 (Russia) | Tore Supra
(France) | DIIID | TFTR | NSTX | ULCEAT | Alcator C-Mod | LDX (all
USA) | H-INF (Ausztralia) | MSAT | START (UK) | ASDEX Upgrade
(Germany) | TCV (Switzerland) | DEMO (Commercial)
Inertial confinement devices.
Laser driven (16)
and non laser
driven (2)
NIF | OMEGA | Novette laser | NIKE laser | Argus laser | Ciclop laser |
Janus laser | Long path laser | 4 laser | Vulcan laser (all USA) |
LMJ | Luli2000 (France) | Gekko XII (Japan) | ISKRA lasers
(Russia) | Asterix IV laser (Czeh Republik) | HiPER (European).
Non laser driven: Z-machine | PACER (USA)
6-10-2009, Hanoi, Vietnam
II.1. Magnetic fusion (ITER) program
• ITER is an international tokamak
(magnetic confinement fusion)
experiment. It builds upon research
conducted on devices such as TFTR,
JET, JT-60, T-15. The program is
anticipated to last for 30 years and
cost € 10 billion. Announced in 2005
that ITER will be built in Cadarache,
France.
• It designed to produce ~ 500 MW of
fusion power sustained for up to 1000
seconds. It is intended to be an
experimental step between today's
studies of plasma physics and future
electricity-producing fusion power
plants (DEMO).
Magnetic fusion has long been
heralded as the future of
renewable energy, but could it
be lasers that hold the key.
6-10-2009, Hanoi, Vietnam
II.2. Laser fusion, inertial confinement.
Indirect fusion (central ignition heavy ion beams or ion beams)
Intense laser beams, focused into a tiny gold cylinder called a hohlraum, will
generate a "bath" of soft X-rays that will compress a tiny hollow shell filled with
DT to 100 times the density of lead. In the resulting conditions – a temperature
of more than millions of degrees and pressures 100 billion times the Earth's
atmosphere – the fuel core will ignite and thermonuclear burn will quickly
spread through the compressed fuel.
In 2010, National Ignition
Facility (NIF) will begin
experiments that will focus
the energy of 192 giant laser
beams on a target filled with
DT fuel. NIF's goal is to fuse
the hydrogen atoms' nuclei
and produce net energy gain.
Chamber is 10 m diameter.
Livermore.
Nova laser opened in 1985 (chamber, 10
laser beams converge to heat and shock a
tiny hohlraum) It is 9 m high and 4.5 m
diameter. Livermore.
6-10-2009, Hanoi, Vietnam
Laser fusion, inertial confinement.
Direct fusion (fast ignition)
• It will capable of firing more
than a petawatt of energy
at a 2 mm fuel pellet held in
place by a bottle. The laser
barrage will compress the
pellet to just a few microns,
that can generate millions
of degrees of heat needed
for fusion to occur.
Compression → Ignition →
Burn
6-10-2009, Hanoi, Vietnam
High Power laser Energy Research facility (HiPER)
•
•
It is the first experiment
designed specifically to study
the "fast ignition„ (direct
fusion) approach to
generating nuclear fusion,
which uses much smaller
lasers than conventional
designs. The design for
possible construction in the
EU starting 2010.
NIF: Input E (1 beam) = 4 MJ.
Output E (1 beam) = 20 MJ.
Output/Input; Q = 5. But the
input E of 192 beams = 330 MJ
(Q< 1). HiPER: Input E = 270 kJ
(driver and heater lasers).
The smaller lasers are much less expensive, therefore the
Output E ~ 25-30 MJ. Q ~ 90 - power-for-cost of HiPER is expected to be about an order
100.
of magnitude less expensive than like NIF.
6-10-2009, Hanoi, Vietnam
The High Average Power Laser Program
Phase I. The goal is to establish the technology
required for the lasers, target fabrication,
target injection, chambers, and final optics,
as well as to identify one or more credible
chamber concepts (2001-2005).
Phase II will provide an integrated demonstration
that the main laser IFE components can
operate together in a predictable manner
and that the performance will scale to a
fusion power plant, (2012).
Phase III is the Engineering Test Facility (ETF). It
would be the first Laser IFE facility to
repetitively produce significant
thermonuclear burn, (2025). It would expect
the laser energy to be between 1.4-2.0 MJ,
with a gain of approximately 120, and a
fusion output of between 160 to 240 MJ.
•
•
Participants (Institutions): DoD/DoE Labs.
(8); Industry (6); University (4).
Laser Inertial Fusion Energy (LIFE). Direct
ignition. A schematic appears below.
6-10-2009, Hanoi, Vietnam
Birds view of the power plant KOYO-F (Japan)
Basic specification of
KOYO-F (direct fusion)
Net output
1200 MWe
(4×300)
Laser Energy
1.1 MJ
Fusion output/pulse
200 MJ
Pulse rep-rate
in reactor
4 Hz
Total output
1519 MWe
Thermal to
electricity effic.
41.5 %
Laser efficiency
11.4 %
Some data: Compression laser Heating laser
Wave length
3ω
1ω
Energy/pulse
1.1 MJ
0.1 MJ
Beam number
32
1 bundle
Rep-rate
16 Hz
16 Hz
6-10-2009, Hanoi, Vietnam
Some Major Laser Fusion Facilities in the World
NIF, LLNL, USA
GEKKO XII-FIREX,
ILE, Osaka, Japan
LMJ, CESTA, Bordeaux,
France
OMEGA-EP, LLE,
Rochester US
6-10-2009, Hanoi, Vietnam
SG-III, Menyang, CAEP,
China
ISKRA-5" laser target
chamber (Russia)
IAEA- FC 2008, 50 years’ Ann. Fusion Res., Oct. 15, 2008, Geneva, SW
(Kunioki Mima, Institute of Laser Engineering, Osaka University)
6-10-2009, Hanoi, Vietnam
Short summary and conclusions
I.
Current critical reactors in operation around the world are generally
considered II- or III-generation systems. Generation IV reactors are a set
of nuclear reactor designs currently being researched. These designs are
generally not expected to be available for commercial construction
before 2030.
II. The subcritical accelerator driven (AD) power plants can also produced
electricity and considerably to diminish the nuclear waste from 2030.
Most important advantage of the ADS is that the reactor coming to
standstill if we switch off the accelerator and with this we can avoid the
very hazardous runaway accidents.
III. Magnetic fusion has long been heralded as the future of renewable
energy, but could it be lasers that hold the key. It is intended to be an
experimental step between today's studies of plasma physics and future
electricity-producing fusion power plants (DEMO).
6-10-2009, Hanoi, Vietnam
IV. Laser fusion power plants are the devices of future. The smaller
lasers are much less expensive, therefore the power-for-cost of
HiPER is expected to be about an order of magnitude less
expensive than like NIF types. Its hopeful that it could become a
commercial reality within the next 20 years.
V. EXPECTED APPLYCATION OF THE IKI-TECHNIQUE
• Control the Burnup calculation
• Studying the asymmetry of the Reactor
• Problems of security of the Reactor.
• Control yield of some fission production
THANK YOU FOR YOUR ATTANTIONS
6-10-2009, Hanoi, Vietnam