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Time-dependent Neutronic Analysis for High Level Waste Transmutation in a Fusion-driven Transmuter

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Abstract

This study presents time-dependent transmutations of high-level waste (HLW) including minor actinides (MAs) and long-lived fission products (LLFPs) in the fusion-driven transmuter (FDT) that is optimized in terms of the neutronic performance per fusion neutron in our previous study. Its blanket has two different transmutation zones (MA transmutation zone, TZMA, and LLFP transmutation zone, TZFP), located separately from each other. High burn-up pressured water reactor (PWR)-mixed oxide (MOX) spent fuel is used as HLW. The time-dependent transmutation analyses have been performed for an operation period (OP) of up to 10 years by 75% plant factor (η) under a first-wall neutron load (P) of 5 MW/m2. The effective half-lives of the MA and LLFP nuclides can be shortened significantly in the considered FDT while substantial electricity is produced in situ along the OP.

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Abbreviations

A :

Area (cm2)

C E :

Energy conversion factor (1.6021 × 10−19 MWs/MeV)

C m :

Ratio of atomic mass to N 0 (g/atom)

E :

Neutron energy (MeV)

E f :

Energy per fission (200 MeV)

k eff :

Neutron multiplication coefficient

M :

Blanket energy multiplication factor

m :

Mass (kg)

n :

Neutron

N :

Atomic density (atoms/cm3)

N a :

Avogadro number (6.023 × 1023 atom/mol)

N x :

Transmuted density of nuclide by x reaction (atom/cm3)

P :

First-wall neutron load (MW/m2)

P th :

Thermal power production (GWth)

R x :

x-Reaction rate (reactions/s)

R x D :

x-Reaction rate density (reactions/cm3/s)

t :

Time (year)

T :

Total operation time (year)

T 1/2 :

Half-life (year)

T 6 :

Tritium breeding ratio from 6Li

T 7 :

Tritium breeding ratio from 7Li

V :

Volume (cm3)

VF:

Volume fraction (%)

BOP:

Beginning of operation period

BU:

Fuel burn-up (GWd/tHM)

B/T :

Burning and/or transmutation

C/C:

Carbon/carbon

D–T:

Deuterium–tritium

EC:

Electron capture

EOP:

End of operation period

FDT:

Fusion-driven transmuter

FW:

First-wall

HLW:

High-level waste

LLFP:

Long-lived fission product

MA:

Minor actinide

MOX:

Mixed oxide

NMZ:

Neutron multiplier zone

OP:

Operation period

PWR:

Pressured water reactor

RZ:

Reflector zone

SZ:

Shielding zone

TBR:

Tritium breeding ratio

TBZ:

Tritium breeding zone

TF:

Transmutation fraction

TR:

Transmutation rate (kg/GWth year)

TRU :

Transuranium

TZ:

Transmutation zone

α:

Alpha particle

β:

Beta decay

\( \phi \) :

Neutron flux (n cm−2 s−1)

γ:

Capture

η:

Plant factor

λ:

Decay constant (1/year)

μ :

Volume fraction

ρ :

Density (g/cm3)

σ:

Microscopic cross-section (cm2)

Δt :

Discrete time interval

Φ:

Number of fusion neutron per second

Γ:

Peak-to-average fission power density ratio

a:

Absorption reaction

c:

Capture reaction

dep:

Depleted

f or F:

Fission

fuel:

Fuel

FP:

Long-lived fission product

fw:

First-wall

i :

Daughter nuclide

j :

Mother nuclide

ji :

From j to i

Li2O:

Lithium oxide

MA:

Minor actinide

max:

Maximum

x :

Transmutation reaction type (one of a, c and f reactions or F)

eff:

Effective

References

  1. M. Üeyli, Transmutation of minor actinides discharged from LMFBR spent fuel in a high power density fusion reactor. Energy Convers. Manage. 45, 3219–3238 (2004)

    Article  Google Scholar 

  2. E.A. Azizov et al., The concept of the volumetric neutron source on the basis of the JUST-T tokamak for minor actinides transmutation. Plasma Devices Oper. 11, 279–286 (2003)

    Article  Google Scholar 

  3. A. Serikov et al., Possibility of fusion power reactor to transmute minor actinides of spent nuclear fuel. Fusion Eng. Des. 63, 93–99 (2002)

    Article  Google Scholar 

  4. K.M. Feng et al., Transmutation of minor actinides in a spherical torus tokamak fusion reactor, FDTR. Fusion Eng. Des. 63, 127–132 (2002)

    Article  Google Scholar 

  5. K.M. Feng, G. Hu, Transmutation of nuclear wastes in a fusion breeder. Fusion Eng. Des. 41, 449–454 (1998)

    Article  Google Scholar 

  6. E.T. Cheng, R.J. Cerbone, Prospect of nuclear waste transmutation and power production in fusion reactors. Fusion Technol. 30, 1654–1658 (1996)

    Google Scholar 

  7. K.M. Feng, G.S. Zhang, Transmutation of transuranic actinides in a spherical torus tokamak fusion reactor. Nucl. Fusion 43, 756–760 (2003)

    Article  ADS  MathSciNet  Google Scholar 

  8. A. Stankovsky et al., Transmutation of long-lived fission products driven by D–T and D–D fusion: specific neutronics and radiological consequences. Fusion Sci. Technol. 43, 569–579 (2003)

    Google Scholar 

  9. M. Saito et al., Fusion-driven transmutation of fission product cesium in its elemental form. J. Nucl. Sci. Technol. 37, 1024–1031 (2000)

    Article  Google Scholar 

  10. M. Saito et al., Transmutation of elemental cesium by a fusion neutron source. Nucl. Technol. 133, 229–241 (2001)

    Google Scholar 

  11. Takibaev et al., Transmutation of zirconium-93 in high-flux blanket of fusion neutron source. J. Nucl. Sci. Technol. 37, 870–876 (2000)

  12. H. Tsutsui et al., Transmutation of fission products by high-field tokamak reactor with force-balanced coils. Fusion Eng. Des. 41, 431–436 (1998)

    Article  Google Scholar 

  13. N.N. Vasiliev et al., Burning of minor actinides and fission products from spent nuclear fuel of power plants in dual-purpose fusion reactor. Plasma Devices Oper. 11, 123–129 (2003)

    Article  Google Scholar 

  14. Y. Gohar, Fusion solution to dispose of spent nuclear fuel, transuranic elements, and highly enriched uranium. Fusion Eng. Des. 58, 1097–1101 (2001)

    Article  Google Scholar 

  15. W.M. Stacey, E.A. Hoffman, Tokamak transmutation facility studies. Fusion Technol. 39, 525–529 (2001)

    Google Scholar 

  16. Y. Gohar, Flibe blanket concept for transmuting transuranic elements and long lived fission products. Fusion Technol. 39, 535–540 (2001)

    Google Scholar 

  17. Y.X. Chen, Y.C. Wu, Conceptual study on high performance blanket in a spherical tokamak fusion-driven transmitter Fusion Eng. Des. 49, 507–512 (2000)

    Article  Google Scholar 

  18. L.J. Qiu et al., A low aspect ratio tokamak transmutation system. Nucl. Fusion 40, 629–633 (2000)

    Article  ADS  Google Scholar 

  19. L.J. Qiu et al., Conceptual desıgn of a fusıon-fıssıon hybrıd reactor for transmutatıon of hıgh-level nuclear waste. Fusion Eng. Des. 25, 167–177 (1994)

    Google Scholar 

  20. H. Yapıcı et al., Minor actinide transmutation potential of modified PROMETHEUS fusion reactor. J. Fusion Energy 23, 121–135 (2004)

    Article  Google Scholar 

  21. H. Yapıcı, M. Übeyli, Power flattening in Prometheus breeder reactor using nuclear fuel and waste actinide. Ann. Nucl. Energy 30, 159–173 (2003)

    Article  Google Scholar 

  22. H. Yapıcı, Burning and/or transmutation of transuraniums discharged from PWR-UO2 spent fuel and power flattening along the operation period in the force free helical reactor. Energy Convers. Manage. 44, 2893–2913 (2003)

    Article  Google Scholar 

  23. H. Yapıcı, Determination of the optimal plutonium fraction in transuranium discharged from pressured water reactor (PWR) spent fuel for a flat fission power generation in the force-free helical reactor (FFHR) along the transmutation period. Ann. Nucl. Energy 30, 633–649 (2003)

    Article  Google Scholar 

  24. H. Yapıcı, Study on transmutation of minor actinides discharged from high burn-up PWR-MOX spent fuel in the force-free helical reactor. Ann. Nucl. Energy 30, 413–436 (2003)

    Article  Google Scholar 

  25. H. Yapıcı, Study of fissile fuel breeding concept for the force-free helical reactor. Fusion Eng. Des. 65, 599–609 (2003)

    Article  Google Scholar 

  26. H. Yapıcı, N. Demir, G. Genç, Neutronic analysis for transmutation of minor actinides and long-lived fission products in a fusion-driven transmuter (FDT), J.Fusion Energy 25(3/4), 225–239 (2006)

    Google Scholar 

  27. NEA, Calculations of Different Transmutation Concepts an International Benchmark Exercise, Nuclear Science Committee (2000)

  28. N.M. Greene, L.M. Petrie, XSDRNPM: A One-Dimensional Discrete-Ordinates Code for Transport Analysis, Sect. F3 of SCALE: A Modular Code System for Performing Standardized Computer Analyses for Licensing Evaluation, NUREG/CR-0200, Rev. 6 (ORNL/NUREG/CSD-2/V2/R6), Vols. I, II, and III. Version 4.4a of the code package is available from Radiation Safety Information Computational Center (RSICC) at Oak Ridge National Laboratory as CCC-545 (2000)

  29. N.M. Greene, J.W. Arwood, R.Q. Wright, C.V. Parks, The LAW Library-A Multi group Cross-Section Library for Use in Radioactive Waste Analysis Calculations, ORNL/TM-12370, Martin Marietta Energy Systems, Inc., Oak Ridge Natl. Lab. (1994)

  30. H. Yapıcı, XSCALC for Interfacing Output of XSDRN to Calculate Integral Neutronic Data, Erciyes University/TURKEY (2001)

  31. H. Yapıcı, XSTRAN for Interfacing Output of XSDRN to Calculate Time Dependent Transmutation of Actinides, Erciyes University/TURKEY, (2002)

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Yapıcı, H., Demir, N. & Genç, G. Time-dependent Neutronic Analysis for High Level Waste Transmutation in a Fusion-driven Transmuter. J Fusion Energ 27, 206–215 (2008). https://doi.org/10.1007/s10894-007-9130-1

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