6-10-2009, Hanoi, Vietnam Researches and applied measurements on nuclear physics and atomic power plants fields in the Institute of Isotopes Árpád VERES

6-10-2009, Hanoi, Vietnam

Researches and applied measurements on nuclear physics and atomic power plants

fieldsin the Institute of Isotopes

Árpád VERESÁrpád VERESScientific advisorScientific advisor

Institute of Isotopes of HASInstitute of Isotopes of HAS 1525 Bp. Pf. 77 1525 Bp. Pf. 77 e-mail: [email protected] e-mail: [email protected]

ContentContentss of lecture of lecture• Research Departments of Institute of IsotopesResearch Departments of Institute of Isotopes..• Nuclear isomers and its applicationsNuclear isomers and its applications..• Present state of nuclear fission power plants. power plants.

(Comparison of IKI-measurements and Paks-(Comparison of IKI-measurements and Paks-calculations for burncalculations for burn up of fuel assembles)up of fuel assembles). . The The electricity and the nuclear wastes produced by critical electricity and the nuclear wastes produced by critical power plantspower plants..

• Accelerator-Driven (spallation), Accelerator-Driven (spallation), subcriticalsubcritical nuclear nuclear fissionfission power plantspower plants..

• Nuclear fusion power plantsNuclear fusion power plants..


http://en.wikipedia.org/wiki/Nuclear_fission


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).

Departments of the Institute and its research areas:

http://www.iki.kfki.hu/radchem/index_en.shtml

http://www.iki.kfki.hu/surfcat/index_en.shtml

http://www.iki.kfki.hu/isoappl/index_en.shtml

Research Reactor 20 MW, water cooled, water moderate, thermal flux 1014 cm-2 s-1

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.


http://www.iki.kfki.hu/nuclear/index_en.shtml





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

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


Nuclear section: Nuclear safeguards; Combating illicit trafficking of nuclear materials; Photo excitation; Reactor

Safeguards measurements of the damaged,re-encapsulated fuel

at Paks Power Plan

Spent Fuel Attribute Tester at Paks Power Plan

(SFAT)


Nuclear section: Age determination of Uranium sample

by gamma-spectrometry

Low-background iron chamber (20 cm wall thickness) with coaxial HPGe detector Large area (~20 cm2) planar HPGe detector

234U

230Th

226Ra

222Rd

218Po

214Pb

214Bi

Clock: 214Bi/234UOther laboratories(mass-spectrometry)

Our laboratory(gamma-

spectrometry)

22.2 - 22.6 years22.4 1.2 years23.5 0.5 years

23 3 years


Neutron coincidence counting: • 3He tubes around the source + • shift register or pulse train register

Neutron detectors(3He tubes)

sourceholder

Moderator

• Total neutron count, T• Coincidence neutrons, R, from

– n-induced fission inside sources– 9Be(n, 2n)8Be reaction– spontaneous fission

• Total neutron count, T• Coincidence neutrons, R, from

– n-induced fission inside sources– 9Be(n, 2n)8Be reaction– spontaneous fission

Nuclear section: Identification Neutron Sources

by neutron coincidence technique: R/T-T method


Nuclear section: PHOTO EXCITATION



Short chronology of nuclear isomersShort chronology of nuclear isomers•1921. Otto Hahn 1921. Otto Hahn observed the isomeric state of observed the isomeric state of 234234Pa from the Pa from the --decay of decay of 234234Th Th

•1935. V. Kurcsatov et al. 1935. V. Kurcsatov et al. produced produced 8080BrBrmm by by (n,(n,)) reaction reaction

•1936. C. F. Weizsäcker 1936. C. F. Weizsäcker recognized that the nuclear isomerism may recognized that the nuclear isomerism may occur whenever the angular momentum of a low-lying state of occur whenever the angular momentum of a low-lying state of nucleus differs from the angular momentum of any lower state by nucleus differs from the angular momentum of any lower state by several units of h/2several units of h/2..

•1938. M. Goldhaber, R. D. Hill, L. Szilard 1938. M. Goldhaber, R. D. Hill, L. Szilard reported conclusive reported conclusive evidence of nuclear isomerism in a stable nucleus. They found that evidence of nuclear isomerism in a stable nucleus. They found that the 4.1 hour the 4.1 hour -- activity of indium could be product by activity of indium could be product by fast neutronfast neutron


•1939. Pontecorvo et al. 1939. Pontecorvo et al. observed isomeric state of stable observed isomeric state of stable 115115In In nuclear by nuclear by x-rayx-ray excitation. excitation.•1939. M. Goldhaber et al. 1939. M. Goldhaber et al. irradiated indium target with the irradiated indium target with the -rays -rays emitted by 0.5 g emitted by 0.5 g 226226Ra to obtain isomeric activity by the Ra to obtain isomeric activity by the 115115InIn((,,’)’)115115InInmm reaction. Negative results. reaction. Negative results.•1954. G. Harbottle 1954. G. Harbottle estimated the activity of estimated the activity of 6o6oCo and of Co and of 182182Ta Ta γγ- - sources from the measured isomeric number of sources from the measured isomeric number of 115115InIn((γ,γ’γ,γ’))115115InInmm reactions.reactions.•1956. N. Ikeda, K. Yoshihara 1956. N. Ikeda, K. Yoshihara measured the cross section (σmeasured the cross section (σexpexp) of ) of 111111CdCdmm and and 115115InInmm by by 6060Co Co γ-source.γ-source. •1963. Á. Veres 1963. Á. Veres also measured the cross section of isomeric state of also measured the cross section of isomeric state of ten stable nuclei ten stable nuclei ((7777SeSemm, , 8787SrSrmm, , 8989YYmm, , 107,109107,109AgAgmm, , 111111CdCdmm, , 115115InInmm, , 179Hfm179Hfm, , 191191IrIrmm, , 195195PtPtmm, , 197197AuAumm, and , and 199199HgHgmm) ) by gamma rays of by gamma rays of 6060Co and Co and estimated its partial level width of activation levels (~1.1 MeV) too. estimated its partial level width of activation levels (~1.1 MeV) too. There where between in the range of 10There where between in the range of 10-4-4-10-10-7-7 eV. eV.


5-09-1962. One of the first measurements of photoactivation of isomers by γ-rays of 60Co. (L. Szirtes, Á. Veres, P. Bedrossián)

Irradiation facilityIrradiation facility

The shows the irradiation and store ↻The shows the irradiation and store ↻position of the source.position of the source.

The shows the install the target in ↥The shows the install the target in ↥irradiation position. irradiation position.

1.1. Target nuclei which are excited Target nuclei which are excited by γ-rays to the isomeric state.by γ-rays to the isomeric state.

2.2. 60Co source (1.3 kCi ~ 48 TBq)60Co source (1.3 kCi ~ 48 TBq)3.3. Lead container (shielding 2.2 Lead container (shielding 2.2

tons)tons)


Ea

Em

Eg


Chart of the isomers of stable nucleiN 43 44 47 49 50 52 56 58 60 62 63 64 65

Z 34

77Sem

17.4 s

35

79Brm

4.9 s

36

83Krm

1.83 h

38

87Srm

2.8 h

39

89Ym

16 s

40 90Zrm

0.8 s

41

93Nbm

16.1 y

43

99Tcm

6.01 h

45

103Rhm

56 m

47

107Agm

44.3 s

109Agm

39.6 s

48

111Cdm

48 m

111Cdm

48 m


N 63 65 67 69 71 73 75 77 79 80 81 99 106Z 49

113Inm

1.7 h

115Inm

4.5 h

50

117Snm

13.6 d

119Snm

293 d

52

123Tem

120 d

125Tem

57.4 d

54

120Xem

8.9 d

131Xem

12 d

56

135Bam

28.7 h

136Ba0.3 s

137Bam

2.6 m

68

167Erm

2.6 m

70

176Ybm

11.4 s

N 105 106 107 108Z 71

176Lum

3.64 h

72

177Hfm2

51 m

178Hfm2

31 y

179Hfm1

18.7 s

180Hfm

5.5 h

73

180Tam

1.2 Py

N 117 118 119

Z 78

195Ptm

4.02 d

79

197Aum

7.73 s

80

199Hgm

43 m,

N 109 113 114 116Z 74

183Wm

5.2 s

76

189Osm

5.8 h

190Osm

10 m

192Osm

6.1 s

77

191Irm

4.9 s

193Irm

10 d

N 122 125 127 143

Z 82

204Pbm

67 m

207Pbm

0.8 s

83

210Bim

3 My

92

235Um

25 m

The codes of colorsThe codes of colors

1 sec to 1 hour1 sec to 1 hour: : 20 20 isomersisomers

scarletscarlet

1 hour to 1 day1 hour to 1 day:: 10 10 isomersisomers

YellowYellow

1 day to 1 year 1 day to 1 year :: 8 8 isomersisomers

greengreen

1 year1 year:: 5 5 isomersisomers

blueblue

It was brought up the question It was brought up the question in the literature, that whether in the literature, that whether the mechanism of the isomeric the mechanism of the isomeric activation has non resonant activation has non resonant character or not.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


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


Explain in other way

without using the non-resonant process Compton effect in shielding-, absorber- material and in target on Resonant flux


Nuclear Power PlantsNuclear Power Plants

Fission Power PlantsFission Power PlantsFusion Power PlantsFusion Power Plants



The present state and perspectives of fission and The present state and perspectives of fission and fusion power plantsfusion power plants

(T(Types of the nuclear power plantsypes of the nuclear power plants))

I. Nuclear fission power plants: power plants: I.1. Critical reactor I.1. Critical reactor convert energy released from the nucleus convert energy released from the nucleus

of an atom, mainly via of of an atom, mainly via of 235235U.U.I.2. Accelerator-driven I.2. Accelerator-driven subcritical reactors subcritical reactors used by used by

transmutation of nuclear wastes as fuel.transmutation of nuclear wastes as fuel.II. Nuclear fusion power plants use the fusion of power plants use the fusion of

deuterium and tritium as fuel. and tritium as fuel. II.1. Magnetic confinement . II.1. Magnetic confinement . Tokamak-driven.Tokamak-driven.II.2. Inertial confinement. II.2. Inertial confinement. Laser-driven. Laser-driven.

http://en.wikipedia.org/wiki/Nuclear_fission

http://en.wikipedia.org/wiki/Fusion_power

http://en.wikipedia.org/wiki/Deuterium


December 2, 1942. December 2, 1942. Nuclear Nuclear reactor reactor Chicago-Pile-1. USA. Chicago-Pile-1. USA. (Led by Enrico Fermi, the (Led by Enrico Fermi, the idea of Leo Szilard). idea of Leo Szilard).

June 27, 1954. June 27, 1954. Nuclear Power Nuclear Power Plant,Plant, USSR, Obninsk. It USSR, Obninsk. It produced 5 MW electric produced 5 MW electric powerpower..

I.1. I.1. The first n-pile and nuclear power plantThe first n-pile and nuclear power plant


The The criticalcritical power plants power plants1.1. Generation I. Early prototype reactors, iGeneration I. Early prototype reactors, i.) 1954, the first nuclear .) 1954, the first nuclear

power plant (5 MW) Obninsk, USSR; ii.) 1956, Calder Hall in Sell power plant (5 MW) Obninsk, USSR; ii.) 1956, Calder Hall in Sell afield, England a gas-cooled Magnox reactor (50 MW, later 200 afield, England a gas-cooled Magnox reactor (50 MW, later 200 MW); iii.) 1957, the Shipping port Reactor (Pennsylvania, USA),MW); iii.) 1957, the Shipping port Reactor (Pennsylvania, USA), pressurized water reactor.pressurized water reactor.

2.2. Generation II. Commercial reactors 1965-95 (more than 400), Generation II. Commercial reactors 1965-95 (more than 400), LWR-LWR-PWR, BWR, CANDU, WWR/RBMK. PWR, BWR, CANDU, WWR/RBMK. (4 VV(4 VVR-440 units of PaksR-440 units of Paks,, HungaryHungary was was installed between 1982-87 installed between 1982-87)* The next 8 slides)* The next 8 slides. .

3.3. Generation III. Generation III. 1995-2010 Temperature Advanced LWRs, System 1995-2010 Temperature Advanced LWRs, System 80+, AP600, EPR. Gen. III+ 2010-2020 Improved economist.80+, AP600, EPR. Gen. III+ 2010-2020 Improved economist.

4.4. Generation IV. Generation IV. Very High Temperature Reactor (VHTR) called Next Very High Temperature Reactor (VHTR) called Next Generation Nuclear Plant (NGNP).Generation Nuclear Plant (NGNP). C Completed 2021. Primary goals: ompleted 2021. Primary goals: improve nuclear safety, proliferation resistance, and to minimize improve nuclear safety, proliferation resistance, and to minimize the nuclear wastesthe nuclear wastes..


*Earlier achievements in Paks (Hungary)•Total safety evaluation of the units was accomplished in 1994. Total safety evaluation of the units was accomplished in 1994. •An efficiency enhancement due to reconstruction of the secondary loop An efficiency enhancement due to reconstruction of the secondary loop and replacements of the turbines increased the original 440 MW of electric 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 power to 470 MW. The total 1790 MW is about 40 % of the Country electricity.electricity.•Between 1996 and 2002 the costs of the Programme of Safety Between 1996 and 2002 the costs of the Programme of Safety Measurements (PSM) amounted to 60 billion Fts. (~ 300 Measurements (PSM) amounted to 60 billion Fts. (~ 300 MM$). The average $). The average sale price of the Paks NPP was 10.16 Ft/kWh in 2008. sale price of the Paks NPP was 10.16 Ft/kWh in 2008. •TThe specific costs of generation of the extra-power, the investment cost he specific costs of generation of the extra-power, the investment cost of the extra-capacity enhancement was shown to be the lowest as of the extra-capacity enhancement was shown to be the lowest as compared to the cost of building new different type power plants.compared to the cost of building new different type power plants.Power plant Power plant Specific investment costs Specific investment costs [bFt/MW][bFt/MW]New lignite 350New lignite 350New gas turbine 125New gas turbine 125Biomass 400Biomass 400Capacity upgrading of Paks NPP ~40Capacity upgrading of Paks NPP ~40


Nuclear section: COMPARISION OF IKI-MEASUREMENTS

AND PAKS-CALCULATION FOR BURNUP OF FUEL

4 block of Paks Nuclear Power plant, Hungary


STRUCTURE OF ONE BLOCK

VVER-440 REACTOR


STRUCTURE OF VVER-440 REACTOR

REACTOR CORE


C-PORCA BURNUP-CALCULATIONFOR EVERY 126-RODS OF ALL-ASSEMBLIESS

126 Rods

FUEL ASSAMBLE

48 Nodes


IKI- BURNUP-MEASUREMENTS MEASUREMENTAL SET UP

HP-Ge detector

Spent fuel assemble

CZT detector

Fission Chamber + Si diode detector

Collimator


A TYPICAL GAMMA SPECTRUM MEASURED BY HP-GERMANIUM DETECTOR

0 500 1000 1500 2000

10

100

1000

Ce-Pr1441489 keV

Cs1341366 keV

Eu1541274 keV

Cs1341168 keV

Ru-Rh1061128 keV

Ru-Rh1061050 keV

(e)

(c)

(d)

(d): Eu154 1005 keV

(e): Cs134 1039 keV

(c): Eu154 873 keV

Cs134802 keV

Cs134795.8 eV

(b): Eu154 723 keV

(b)

(a)

(a): Ce-Pr144 696.6 keV

Cs137661.7 keV

Ru-Rh106622 keV

Cs134604,7 keV

Ru-Rh106512 keV

Co

uts

Energy (keV)


THE RESULT OF 56993-ASSEMBLE56993 Axial frofile

0

10

20

30

1700 2200 2700 3200 3700 4200 4700

Vertical position

Cs1

37

0

10

20

30

BU

cal

cula

tio

n

Mear.Cps

számolt

24.pozíció él

0

10

20

30

401

2

3

4

5

6

56993 3.bl. 4. Radius profile

0

0,1

0,2

0,3

0,4

0,5

0,6

0,7

-180 -120 -60 0 60 120 180

szög

Cs1

34/C

s137

0

10

20

30

40

50

BU

cal

cula

tio

n

326

350

cal..

ComparisonComparison

EXPECTEDEXPECTED A APPLYCATION PPLYCATION OF THE IKI-TECHNIQUEOF THE IKI-TECHNIQUE•Control the Burnup Control the Burnup calculationcalculation•Studying the asymmetry of Studying the asymmetry of the Reactor the Reactor •Problems of security of the Problems of security of the Reactor.Reactor.•Control yield of some fission Control yield of some fission productionproduction


The electricity andThe electricity and the the nuclear wastes produced by nuclear wastes produced by critical power plantscritical power plants

1.1. In 2007 operated 440 power plants in In 2007 operated 440 power plants in 32 countries of 32 countries of the the world and produced 370 GW-year world and produced 370 GW-year (~2.6×10(~2.6×101212 kWh). kWh). This This is about 16 % of the world's electricity.is about 16 % of the world's electricity.

2.2. If we assume the above level of global nuclear power If we assume the above level of global nuclear power generation, then in the year 2015 there will be more generation, then in the year 2015 there will be more then then 250 000 tons 250 000 tons of spent fuels worldwide, containing of spent fuels worldwide, containing over over 2000 tons of weapons-usable Pu. 2000 tons of weapons-usable Pu. Over Over 70 000 tons 70 000 tons of this spent fuel of this spent fuel (<500 t of Pu) (<500 t of Pu) will be in the USA, will be in the USA, > 1/3 > 1/3 in Russia and in Russia and < 1/3 < 1/3 in Europe and others.in Europe and others.


The amount of TrU and fission productThe amount of TrU and fission productss in 1 ton in 1 ton spent fuel (33 MWd/kg) [g/t]spent fuel (33 MWd/kg) [g/t]

TrU TTrU T1/21/2 (y) [g/t] (y) [g/t]239239Pu 24 400 Pu 24 400 5450*5450*237237Np 2 100 000 Np 2 100 000 450450243243Am 7 400 Am 7 400 100100245245Cm 8 500 Cm 8 500 1,21,2

* Total: Pu : 9 700* Total: Pu : 9 700

Fp. TFp. T1/21/2 (y) [g/t] (y) [g/t]

9999Tc 210 000 Tc 210 000 810810

135135Cs 2 300 000 Cs 2 300 000 360360

129129I 16 000 000 I 16 000 000 170170

The problem: Nuclear waste from commercial power plants The problem: Nuclear waste from commercial power plants contains large quantities of Pu, other fissionable actinides, and contains large quantities of Pu, other fissionable actinides, and long-lived fission product that create challenges for storage and long-lived fission product that create challenges for storage and that are potential hathat are potential hazzardous proliferation concerns.ardous proliferation concerns.


I.I.2.2. Accelerator-Driven (spallation), Accelerator-Driven (spallation), subcriticalsubcritical power plants power plants

The spallation is a high-energy nuclear reaction in which a target The spallation is a high-energy nuclear reaction in which a target nucleus struck by an incident particle of energy (usually < 500 MeVnucleus struck by an incident particle of energy (usually < 500 MeV)) ejects numerous lighter particles and becomes a product nucleus ejects numerous lighter particles and becomes a product nucleus correspondingly lighter than the original nucleus. correspondingly lighter than the original nucleus.


The neutron-yields The neutron-yields of heavy elements of heavy elements (U, W, Pb) (U, W, Pb) produced produced by 0.5-5 GeV protonby 0.5-5 GeV proton energyenergy [Y = 18-45 [Y = 18-45 neutrons per neutrons per proton].proton].

0

5

10

15

20

25

30

35

40

45

50

0 0,5 1 1,5 2 2,5 3 3,5 4 4,5 5

Sec

un

d n

eutr

on

s (n

/GeV

)

Protonenergy (GeV)

U-238

W

Pb

The accelerator can drive 2×500 MWe power plants by transmutation The accelerator can drive 2×500 MWe power plants by transmutation of of 400 kg/year400 kg/year of of 239239PuPu andand 100 kg/year100 kg/year of of other fissionable actinides. other fissionable actinides.


A block diagram of acceleratorA block diagram of accelerator and ATW and ATW configuration configuration


USA concept for the transmutation of spent fuel nuclear wastes.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 On 2036 year the amount of spent fuels will be: > 86 000 ton, in which the most problematic fission products are the which the most problematic fission products are the 9999Tc (93 t) and Tc (93 t) and the the 129129I (20 t).I (20 t).The ATW systems could be used in a series of different scenariosThe ATW systems could be used in a series of different scenarios. .


Time schedule and milestones for the development of an accelerator Time schedule and milestones for the development of an accelerator driven systems (ADS) and accelerator driven transmutation (ADT) driven systems (ADS) and accelerator driven transmutation (ADT)

technology in Europetechnology in Europe


Some Accelerator-DrivenSome Accelerator-Driven programs for programs for Transmutations of nuclear wastesTransmutations of nuclear wastes

•1987. CERN, JRC (Dubna), BNL (13-28 MeV p1987. CERN, JRC (Dubna), BNL (13-28 MeV protonroton-cyclotrone, TRU -cyclotrone, TRU target/fuel, 900 MWtarget/fuel, 900 MWtt •1989. JAERI (Japan) OMEGA project salt-solution target1989. JAERI (Japan) OMEGA project salt-solution target•1990. BNL PHOENIX project, 1,6 GeV-104 mA p-linac1990. BNL PHOENIX project, 1,6 GeV-104 mA p-linac•1991. LANL ATW, 101991. LANL ATW, 101616 n/cm n/cm22s, 100-180 MeV p-linac, actinide fuel.s, 100-180 MeV p-linac, actinide fuel. •1993. CERN (Rubbia), 0,8 GeV-6,25 mA accelerator as driver for a 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. power reactor a target with thorium as fuel and lead as a coolant. •1996. Belgium, MYRHA project, 250 MeV-2 mA proton-1996. Belgium, MYRHA project, 250 MeV-2 mA proton-ccyclotrone. n yclotrone. n ~1,5×10~1,5×101515 n/cm n/cm22, the volume of zone: 35 cm, the volume of zone: 35 cm33 •Many institute of 12 Countries co-operate in 20 project.Many institute of 12 Countries co-operate in 20 project.

FUSION POWER PLANTS


II. Nuclear fusion power plantsII. Nuclear fusion power plants Magnetic Fusion Energy (MFE). Inertial Fusion Energy (IFE).

Fusion is the joining Fusion is the joining together of small, light together of small, light nuclei to form a larger, nuclei to form a larger, more massive nucleus more massive nucleus (the (the deuterium-tritium is the deuterium-tritium is the most popular reaction, but most popular reaction, but there are others).there are others).

The The problemproblem is that is that combination of high temperatures and densities combination of high temperatures and densities are required to force positively charged nuclei together, but the are required to force positively charged nuclei together, but the resulting high pressure will tend to blow fusion plasma (hot ionized resulting high pressure will tend to blow fusion plasma (hot ionized gas) apartgas) apart..


The E.U.’s backing for fusion goes beyond HIPER. By 2016, a reactor that uses non-laser, conventional superconducting magnetic “hot fusion” techniques is expected to be operational in France.

Fusion MethodsFusion Methods: : 3 primary plasma confinement.3 primary plasma confinement.i.i.Magnetic confinement;Magnetic confinement; ii.ii. Gravitational confinement -- astrophysical contexts; Gravitational confinement -- astrophysical contexts; iii.iii.Inertial confinementInertial confinement -- inertia of the fuel confines it for the nanoseconds -- inertia of the fuel confines it for the nanoseconds (10(10-9-9 s) required for the fusion reaction to proceed s) required for the fusion reaction to proceed..

Difference between Difference between magneticmagnetic-- and and inertial confinement:inertial confinement:1.1. In In magnetic confinementmagnetic confinement, the tendency of the hot plasma to expand is , the tendency of the hot plasma to expand is

counteracted by the counteracted by the Lorenz force Lorenz force between currents in the plasma and between currents in the plasma and magnetic fields produced by external coils. The particle densities tend to magnetic fields produced by external coils. The particle densities tend to be in the range of be in the range of 10101818 to 10 to 102222 m m-3-3 and the linear dimensions in the range and the linear dimensions in the range of of 0.1 to 10 m.0.1 to 10 m.

2.2. In contrast, with In contrast, with inertial confinementinertial confinement, there is nothing to counteract the , there is nothing to counteract the expansion of the plasma. The confinement time is simply the time it expansion of the plasma. The confinement time is simply the time it takes the plasma pressure to overcome the takes the plasma pressure to overcome the inertiainertia of the particles, hence of the particles, hence the name. The densities tend to be in the range of the name. The densities tend to be in the range of 10103131 to 10 to 103333 m m-3-3 and the and the plasma radius in the range of plasma radius in the range of 1 to 100 micrometers. 1 to 100 micrometers.


Types of fusion Methods of fusing nucleiMethods of fusing nucleiMagnetic confinement

Tokamak – Spheromack – Stellator – Reversed fiel pinch – Field-Revised 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 experimentsList 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 confine-ment devices. Laser driven (16) and non laser driven (2)

NIF | OMEGA | Novette laser | NIKE laser | Argus laser | Ciclop laser | Janus laser | Long path laser | 4laser | 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)


II.1.II.1. Magnetic fusion (ITER) program Magnetic fusion (ITER) program • ITER is an international ITER is an international tokamak tokamak

((magnetic confinement fusion) magnetic confinement fusion) experiment. It builds upon research experiment. It builds upon research conducted on devices such as TFTR, conducted on devices such as TFTR, JET, JT-60, T-15JET, JT-60, T-15.. The program is The program is anticipated to last for 30 years and anticipated to last for 30 years and cost € 10 billion. cost € 10 billion. AAnnounced in 2005 nnounced in 2005 that ITER will be built in Cadarache, that ITER will be built in Cadarache, France. France.

• It It designed to produce designed to produce ~~ 500 MW of 500 MW of fusion power sustained for up to 1000 fusion power sustained for up to 1000 secondsseconds.. IIt is intended to be an t is intended to be an experimental step between today's experimental step between today's studies of plasma physics and future studies of plasma physics and future electricity-producing fusion power electricity-producing fusion power plantsplants (DEMO). (DEMO).

Magnetic fusion has long been Magnetic fusion has long been heralded as the future of heralded as the future of renewable energy, but could it renewable energy, but could it be lasers that hold the keybe lasers that hold the key..


IIII..2.2. Laser fusion, Laser fusion, inertial confinementinertial confinement. . Indirect fusion (central ignition heavy ion beams or ion beams)Indirect fusion (central ignition heavy ion beams or ion beams)

Nova laser opened in 1985 (chamber, 10 Nova laser opened in 1985 (chamber, 10 laser beams converge to heat and shock a laser beams converge to heat and shock a tiny hohlraum) It is 9 m high and 4.5 m tiny hohlraum) It is 9 m high and 4.5 m diameter. Livermore.diameter. Livermore.

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. Chamber is 10 m diameter. Livermore.Livermore.

Intense laser beams, focused into a tiny gold cylinder called a hohlraum, will 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 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 DT to 100 times the density of lead. In the resulting conditions – a temperature of more than millionof more than millions ofs of degrees and pressures 100 billion times the Earth's degrees and pressures 100 billion times the Earth's atmosphere – the fuel core will ignite and thermonuclear burn will quickly atmosphere – the fuel core will ignite and thermonuclear burn will quickly spread through the compressed fuel. spread through the compressed fuel.


• It will capable of firing more It will capable of firing more than a petawatt of energy than a petawatt of energy at a 2 mm fuel pellet held in at a 2 mm fuel pellet held in place by a bottle. The laser place by a bottle. The laser barrage will compress the barrage will compress the pellet to just a few micronspellet to just a few microns,, that can generate millions that can generate millions of degrees of heat needed of degrees of heat needed for fusion to occur. for fusion to occur. Compression Compression → Ignition → Ignition → Burn→ Burn

Laser fusion, Laser fusion, inertial confinementinertial confinement.. Direct fusion (fast ignition)Direct fusion (fast ignition)


High Power laser Energy Research facility (HiPER)High Power laser Energy Research facility (HiPER)• It is the first experiment It is the first experiment

designed specifically to study designed specifically to study the "fast ignition„ (direct the "fast ignition„ (direct fusion) approach to fusion) approach to generating nuclear fusion, generating nuclear fusion, which uses much smaller which uses much smaller lasers than conventional lasers than conventional designs. The design for designs. The design for possible construction in the possible construction in the EU starting 2010.EU starting 2010.

• NIF: Input E (1 beam) = 4 MJ. NIF: Input E (1 beam) = 4 MJ. Output E (1 beam) = 20 MJ. Output E (1 beam) = 20 MJ. Output/Input; Output/Input; Q = 5. Q = 5. But the But the input E of 192 beams = 330 MJ input E of 192 beams = 330 MJ (Q< 1).(Q< 1). HiPER: Input E = 270 kJ HiPER: Input E = 270 kJ (driver and heater lasers). (driver and heater lasers). Output E ~ 25-30 MJ. Output E ~ 25-30 MJ. Q ~ 90 -Q ~ 90 -100.100.

The smaller lasers are much less expensive, therefore the The smaller lasers are much less expensive, therefore the power-for-cost of HiPER is expected to be about an order power-for-cost of HiPER is expected to be about an order of magnitude less expensive thanof magnitude less expensive than like like NIF. NIF.


The High Average Power Laser ProgramThe High Average Power Laser ProgramPhase IPhase I.. The goal is to establish the technology The goal is to establish the technology

required for the lasers, target fabrication, required for the lasers, target fabrication, target injection, chambers, and final optics, target injection, chambers, and final optics, as well as to identify one or more credible as well as to identify one or more credible chamber concepts (2001-2005). chamber concepts (2001-2005).

Phase II will provide an integrated demonstration Phase II will provide an integrated demonstration that the main laser IFE components can that the main laser IFE components can operate together in a predictable manner operate together in a predictable manner and that the performance will scale to a and that the performance will scale to a fusion power plant, (2012).fusion power plant, (2012).

Phase III is the Engineering Test Facility (ETF). It Phase III is the Engineering Test Facility (ETF). It would be the first Laser IFE facility to would be the first Laser IFE facility to repetitively produce significant repetitively produce significant thermonuclear burn, (2025). Itthermonuclear burn, (2025). It would expect would expect the laser energy to be between 1.4-2.0 MJ, the laser energy to be between 1.4-2.0 MJ, with a gain of approximately 120, and a with a gain of approximately 120, and a fusion output of between 160 to 240 MJ. fusion output of between 160 to 240 MJ.

• Participants (Institutions): DoD/DoE Labs. Participants (Institutions): DoD/DoE Labs. (8); Industry (6); University (4).(8); Industry (6); University (4).

• Laser Inertial Fusion Energy (LIFE). Laser Inertial Fusion Energy (LIFE). Direct Direct ignition. ignition. A schematic appearsA schematic appears below below..


Birds view of the power plant KOYO-F (Japan)Birds view of the power plant KOYO-F (Japan)

Basic specification of Basic specification of KOYO-F (direct fusion)KOYO-F (direct fusion)Net outputNet output 1200 1200

MWMWee (4×300)(4×300)

Laser EnergyLaser Energy 1.1 MJ1.1 MJ

Fusion out-Fusion out-put/pulseput/pulse

200 MJ200 MJ

Pulse rep-rate Pulse rep-rate in reactorin reactor

4 Hz4 Hz

Total outputTotal output 1519 MW1519 MWee

Thermal to Thermal to electricity electricity effic.effic.

41.5 %41.5 %

Laser Laser efficiencyefficiency

11.4 %11.4 %

Some data: Compression laser Heating laserSome data: Compression laser Heating laserWave length 3ω 1ωWave length 3ω 1ωEnergy/pulse Energy/pulse 1.1 MJ 1.1 MJ 00.1.1 MMJJBeam number Beam number 32 1 bundle32 1 bundleRep-rate 16 Hz 16 HzRep-rate 16 Hz 16 Hz


Some Major Laser Fusion Facilities in the WorldSome Major Laser Fusion Facilities in the World

NIF, LLNL, USA LMJ, CESTA, Bordeaux,

FranceSG-III, Menyang, CAEP,

China

GEKKO XII-FIREX, ILE, Osaka, Japan

OMEGA-EP, LLE, Rochester US

ISKRA-5" laser target chamber

(Russia)


IAEA- FC 2008, 50 years’ Ann. Fusion Res.IAEA- FC 2008, 50 years’ Ann. Fusion Res.,, Oct. Oct. 15, 2008, Geneva, SW15, 2008, Geneva, SW (Kunioki Mima, Institute of Laser Engineering, Osaka University)


Short summary and conclusionsShort summary and conclusionsI.I. Current Current critical critical reactors in operation around the world are generally reactors in operation around the world are generally

considered II- or III-generation systems. Generation IV reactors are a set considered II- or III-generation systems. Generation IV reactors are a set of nuclear reactor designs currently being researched. These designs are of nuclear reactor designs currently being researched. These designs are generally not expected to be available for commercial construction generally not expected to be available for commercial construction before 2030. before 2030.

II.II. The The subcriticalsubcritical accelerator driven (AD) power plants can also produced accelerator driven (AD) power plants can also produced electricity and considerably to diminish the nuclear waste from 2030. electricity and considerably to diminish the nuclear waste from 2030. Most important advantage of the ADS is that the reactor coming to 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 standstill if we switch off the accelerator and with this we can avoid the very hazardous runaway accidents.very hazardous runaway accidents.

III.III. Magnetic fusion has long been heralded as the future of renewable Magnetic fusion has long been heralded as the future of renewable energy, but could it be lasers that hold the key. energy, but could it be lasers that hold the key. It is intended to be an It is intended to be an experimental step between today's studies of plasma physics and future experimental step between today's studies of plasma physics and future electricity-producing fusion power plants (DEMO).electricity-producing fusion power plants (DEMO).


IV.IV. Laser fusion power plants are the devices of future. The smaller Laser fusion power plants are the devices of future. The smaller lasers are much less expensive, therefore the power-for-cost of lasers are much less expensive, therefore the power-for-cost of HiPER is expected to be about an order of magnitude less HiPER is expected to be about an order of magnitude less expensive than like NIF types. Its hopeful that it could become a expensive than like NIF types. Its hopeful that it could become a commercial reality within the next 20 years.commercial reality within the next 20 years.

V.V. EXPECTEDEXPECTED A APPLYCATION OF THE IKI-TECHNIQUEPPLYCATION OF THE IKI-TECHNIQUE• Control the Burnup calculationControl the Burnup calculation• Studying the asymmetry of the Reactor Studying the asymmetry of the Reactor • Problems of security of the Reactor.Problems of security of the Reactor.• Control yield of some fission productionControl yield of some fission production

THANK YOU FOR YOUR ATTANTIONSTHANK YOU FOR YOUR ATTANTIONS

Documents

6-10-2009, Hanoi, Vietnam Researches and applied measurements on nuclear physics and atomic power plants fields in the Institute of Isotopes Árpád VERES