DEN/UFMG STUDIES FOR SPENT FUEL OPTIONS - PowerPoint Presentation

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DEN/UFMG STUDIES FOR SPENT FUEL OPTIONS

Carlos E. Velasquez, Graiciany P. Barros, Fabiano Cardoso, Anderson A.P. Macedo, Maria A. F. Veloso, Antonella L. Costa, Angela Fortini, Victor Faria, Fernando Pereira, Claubia Pereira

Joint ICTP-IAEA Workshop on Radiation Effects in Nuclear Waste Forms

and their Consequences for Storage and Disposal

12-16 September

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Nuclear Energy in Brazil

Currently, there are two reactors operating Angra I and Angra II, in Brazil. The third reactor Angra III is under construction.The nuclear contribution to the electricity generation is about 1.4%

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Thorium reserves

Thorium is a valuable resource since it is about three to four times more abundant in the earth’s crust than uraniumBrazil has the third world thorium reserve.

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OECD NEA & IAEA Uranium 2011: Resources,

Production and Demand (Red Book) 2011

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(INCT) National Institute of science and technology of innovative nuclear reactors

MissionAccomplish exploiting the nuclear natural resources especially uranium Research and development of new nuclear technology Human resources trainingPromote nuclear energy for public acceptance

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Nuclear Engineering Department DEN/UFMG

The nuclear engineering department (DEN) called PCTN at UFMG was founded in 1968.The PCTN commitment is to deepen the professional and academic knowledge in the nuclear area.Training students in the nuclear research

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Study Fields

Nuclear Reactor and Nuclear Fuel Cycle TechnologyReactor and nuclear fuel cycle physicsSub-critical and minor actinide systemsLong-lived fission products recycleHigh temperature reactorAdvanced PWRThermal-hydraulic analysisThorium fuel cycle investigations

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The Issue of Nuclear Energy

Since the beginning of the nuclear fission era, SNF or nuclear waste has been produced.The majority of the spent fuel goes to a final repository far away and secures enough to the population contact.Nevertheless, the storage capacity eventually wont be enough, not to mention the expenses to take care of it are high.

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http://www.glogster.com/jerrodhall/nuclear-waste/g-6maemkvce2okra5ricpvpa0

https://www.bartlett.ucl.ac.uk/energy/news/paul-dorfman-nuclear

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Goals of this work

Exploit the nuclear resourcesStudy the reutilization of spent fuelProposed the thorium utilization and fuel regenerationEnhance transmutation of Minor Actinides in a fast spectrum

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http://www.ctr-tech.com/summer06.htm

http://www.the-weinberg-foundation.org/learn/next-gen/thorium/

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Research Proposals

Use reprocessing techniques toSeparate the uranium and plutoniumSeparate the MA together with Pu then spiked with depleted U or ThIrradiate the reprocessed fuel in nuclear systems with a hardness spectrumFusion-Fission SystemAccelerator Driven SystemGen-IV Reactors

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Fission Probability

Neutron Energy (MeV)

2 MeV

14.1 MeV

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Stages

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Choose a SNF matrix

Choose the Reprocessing technique

The irradiation system

Results Analysis

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Typical Spent Fuel type C from a PWR, burnup 33000MWD/THM

ACTINÍDESFission ProductsMass Fractiontotal=0.9785Total mass fractionl=0.0215NuclídeoNuclidesNuclidesU234HAgU235LiCdU236BeInU238CSnNp237CoSbPu238NiTePu239CuIPu240ZnXePu241GaCsPu242GeBaAm243AsLaOthersSeCeBrProthersKrNdHe4RbPmTh230SrSmU233YEuU237ZrGdNp238NbTbNp239MoDyAm241TcHoAm242RuErCm242RhTmCm244PdYbCm245 TOTAL 1.000E+00

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Reprocessing Techniques

UREX+Recover uranium at 99.9% and technetium with 99%. The others percentages recovered are : Pu 99.50%, Np 71%, Am 98% and Cm 79% from the spent fuel matrixGANEXactinides higher than 99.5%lanthanides in the actinide product was around 5% at the end.

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Miguirditchian M., et al., "Development of the ganex process for the reprocessing of gen IV spent nuclear fuels," in ATALANTE 2008, Montipellier (2008).

George F.

Vandegrift

, et al.,

"Designing and Demonstration of the UREX+ Process Using Spent Nuclear Fuel," in

ATALANTE2004

, Nimes (2004).

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Beginning of Cycle

Thorium

FFSADSVHTRPWRNuclide(%)(%)(%)(%)Thorium60.0072.166.8184.37Uranium-0.16-3.51Neptunium0.920.830.70-Plutonium25.6914.1819.36-Americium1.360.311.03-Curium0.090.090.07-Fissile Material2010.27154

Uranium

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FFS

ADS

VHTR

PWR

Nuclide

(%)

(%)

(%)

(%)

-

-

-

-

-

Uranium

60.00

46.26

67.18

88

Neptunium

0.92

2.24

0.69

-

Plutonium

25.69

37.9

19.20

-

Americium

1.36

0.84

1.02

-

Curium

0.09

0.24

0.07

-

Fissile material

20

27.57

15

3-4

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Irradiation

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Further progression as shown in Uranium irradiation

Formation of higher Actinides for

232Th

An introduction to the engineering of fast nuclear reactor, Anthony M. Judd

Formation of Higher Actinides from

238

U

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Nuclear Systems

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Fusion-Fission System

ADS

Gen-IV Reactors

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Multiplication factor

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Fusion Fission System

ADS

VHTR

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Nuclear System

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Vaccum Chamber

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Neutron Spectra

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Fusion Fission

spectrum

ADS spectrum

Fission

Chain spectrum

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FFS After Irradiation

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Fuel: UREX+ spiked with thorium

Power: 3000MWt

Transmutation 7.76

%

Irradiation Time: 10 years

Mass variation under irradiation for the FFS

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ADS after Irradiation

Fuel GANEX spiked Thorium

Irradiation time:10 yearsPower 500MWtTransmutation 11.6%

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Mass variation under irradiation for the

ADS

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VHTR after Irradiation

Fuel: UREX+ spiked with thoriumPower 600MWIrradiation Time : 2.738 years

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Mass variation under irradiation for the VHTR

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Ingestion Toxicity

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Total ingestion hazard for spent fuel materials

Ingestion hazard for each reactor a)PWR, b)VHTR, c)ADS

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Conclusions

These results represent part of the activities performed at DEN/UFMG using reprocessed fuel spiked with thorium in different nuclear systems. The results shows the mass variation at the end of the burnup. Hybrids reactors due to their external neutron source were planned to have longer irradiation times than others reactors. Some studies about different reprocessing techniques are being studied to enhance nuclear fuel cycles in advanced reactors, as well as, the transmutation of minor actinides as am option in systems with hardness spectrum such as gen-IV reactors and hybrid systems.

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REFERENCES

[1] Agência Nacional de Energia Elétrica, "Energia Nuclear"; [Online]. Available: http://www2.aneel.gov.br/arquivos/PDF/atlas_par3_cap8.pdf.[2] Eletrobas - Electronuclear, "Angra 3: energia para o crescimento do país"; [Online]. Available: http://www.eletronuclear.gov.br/aempresa/centralnuclear/angra3.aspx. [Accessed 2016].[3] CNPq, "Instituto Nacional de Ciência e Tecnologia de Reatores Nucleares Inovadores"; INCT, 2008. [Online].Available: ttp://estatico.cnpq.br/programas/inct/_apresentacao/inct_reatores_nucleares.html.[4] G.F. VANDERGRIFT, M.C., REGALBUTO, S.B. AASE, A. ARAFAT, "Lab-scale demonstration of the UREX+ process"; in 4th WM Conference, Tucson, (2004)[5] M. Miguirditchian, L. Chareyre, X. Heres, C. Hill, P. Baron, M. Masson, “GANEX: Adaptation of the DIAMEX-SANEX Process for the Group Actinide Separation"; in GLOBAL 2007, Advanced Nuclear Fuel Cycles and Systems Idaho (2007).[6] F. Cardoso, C. Pereira, M. A. F. Veloso, C. A. M. Silva, R. Cunha, A. L. 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Pereira, "Neutronic evaluation of the non-proliferating reprocessed nuclear fuels in pressurized water reactors," Annals of Nuclear Energy, vol. 24, pp. 829-834 (1997).[17] George F. Vandegrift, Monica C. Regalbuto, Scott Aase, Allen Bakel, Terry J. Battisti,* Delbert Bowers, James P. Byrnes, Mark A. Clark, Dan G. Cummings,* Jeff W. Emery, John R. Falkenberg, Artem V. Gelis, Candido Pereira, Lohman Hafenrichter, Yifen Tsai, Kevin J. Quigley, and Mark H. Vander Pol, "Designing and Demonstration of the UREX+ Process Using Spent Nuclear Fuel," in ATALANTE2004, Nimes (2004).[18] Miguirditchian M., Chareyre L., Sorel C., Bisel I., "Development of the ganex process for the reprocessing of gen IV spent nuclear fuels," in ATALANTE 2008, Montipellier (2008).[19] Barros Graiciany, Velasquez Carlos, Pereira Claubia, Maria A. F. Veloso, Antonella Costa, "Depletion evaluation of an ADS using reprocessed fuel"; International Journal of Hydrogen Energy, vol. 40, no. 44, pp. 15148-15152 (2015).[20] Hans A. Bethe, "The fusion hybrid," Physics Today, pp. 44-51 (1979).[21] Carlos E. Velasquez, Claubia Pereira, Maria A. F. Veloso, Antonella L. Costa, "Layer Thickness Evaluation for Transuranic Transmutation in a Fusion-Fission System," Nuclear Engineering and Design, vol. 286, pp. 94-103 (2015).[22] H. T. D. Poston, “User’s Manual, Version 2.0 for Monteburns”, Los Alamos National Laboratory, LA-UR-99-4999 (1999).[23] X-5 Monte Carlo Team, “MCNP A General Monte Carlo N-Particle Transport Code, Version 5, vol. II. User’s Guide University of California”, Los Alamos National Laboratory (2003).[24] A. Croff, «A User’s Manual for the Origen2 Computer Code,» Oak Ridge National Laboratory (1980).[25] C.D. Bowman, E.D. Arthur, P.W. Lisowski, G.P. Lawrence, R.J. Jensen, J.L. Anderson, B. Blind, M. Cappiello, J.W. Davidson, T.R. England, L.N. Engel, R.C. Haight, H.G. Hughes III, J.R. Ireland, R.A. Krakowski, R.J. LaBauve, B.C. Letellier, R.T. Perry, G.J. Russell, K.P. Staudhammer, G. Versamis, W.B. Wilson "Nuclear Energy Generation and Waste Transmutation Using an Accelerator-Driven Intense Thermal Neutron Source," Nuclear Instruments and Methods, vol. A320, pp. 336-367 (1992).[26] C. Rubbia, J.A.Rubio, S.Buono, N.Fietier, J.Galvez, C.Geles, Y.Kadi, R.Klapisch, P.Mandrillon, J.P.Revol, Ch.Roche, "Conceptual Design of a fast neutron operated high power energy amplifier”, European Organization for Nuclear Research, CERN/AT/95-44 (ET), Geneva (1995).[27] Graiciany P. Barros, Claubia Pereira, Maria A. F. Veloso, Antonella L. Costa, "Fast Accelerator Driven Subcritical System for Energy Production Using Burned Fuel," Fusion Science and Technologu, vol. 61, pp. 256-261 (2012).[28] Tim Abram, Sue Ion, "Generation-IV nuclear power: A review of the states of the science," Energy Policy, vol. 36, pp. 4323-4330 (2008).[29] Anderson A. P. Macedo, Carlos E. Velasquez, Claubia Pereira, C.A.M. Da Silva, "NEUTRONIC PERFORMANCE OF (U, Pu)C FUEL IN A LATTICE OF GFR USING SCALE 6.0," MRS Proceedings (2016).[30] S. M. Bowman, M. E. Dunn, “SCALE Coss-Section Libraries”, OAK Ridge National Laboratory, (2009).[31] M. D. DeHart, “TRITON: A two-Dimentional Transport and Depletion Module for”, OAK Ridge National Laboratory (2009).[32] F. Cardoso, A. Fortini, C. Pereira, A. L. Costa, M. A. F. Veloso, C. A. M. da Silva, “High-Temperature Gas Reactor with Transuranic Fuels," in Proceedings of the 2016 International Congress on Advances in Nuclear Power Plants, San Francisco (2016).

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Acknowledgment

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Thank you for your attention…..

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-mail:

carlosvelcab@ufmg.br

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carlosvelcab@hotmail.com

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- http

://lattes.cnpq.br/6004097335998698

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v- https

://www.researchgate.net/profile/Carlos_Velasquez_Cabrera