Nuclear Performance of Accelerator-Driven Systems with Infinite U - - PowerPoint PPT Presentation

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Nuclear Performance of Accelerator-Driven Systems with Infinite U - - PowerPoint PPT Presentation

May 09, 2023 699 likes •1.6k views

Nuclear Performance of Accelerator-Driven Systems with Infinite U ranium Material Smer AHN 1 , Baar ARER 2 Yurdunaz EL K 3 1 Atlm University, Faculty of Engineering, Ankara 2 Gazi University, Faculty of Science, Ankara 3 Gazi

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Nuclear Performance of Accelerator-Driven Systems with Infinite Uranium Material

Sümer ŞAHİN1,Başar ŞARER2 Yurdunaz ÇELİK3

1Atılım University, Faculty of Engineering,

Ankara

2Gazi University, Faculty of Science, Ankara 3Gazi University, Institute of Science and

Technology, Ankara

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WORLD NUCLEAR POWER PLANTS CONCENTRATION

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750 000 000 people have even not seen electrical light throughout their life !!!

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Accelerator-driven systems (ADS)

 Bombardment of heavy nuclei (A >

200) with high energetic protons (~400 MeV up to 1.5 GeV)

 Spallation neutrons from thermal up to

GeV range with maximum by 1-2 MeV

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NUCLEAR MODELS Spallation reactions proceed through three successive stages:

  • pre-equilibrium stage
  • evaporation-fission stage
  • intranuclear cascade stage (INC)

There are several criteria to discriminate the different intra-nuclear cascade models such as the medium, the collision, the stopping time, the nuclear surface and the Pauli blocking.

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Options offered in the MCNPX code based on physics packages

Bertini, ISABEL, INCL4: Intra-nuclear models Dresner, ABLA: Evaporation-fission models CEM2k: Cascade-exciton model

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Bertini and ISABEL cascade- evaporation models use the “strict” application of the Pauli principle. Fast particles are tracked down to a cutoff energy, usually <10 MeV above the Fermi energy. INCL4 model uses the “statistical”

  • application. Duration of the cascade

stage is determined with calculation time.

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Basic Assumption of Nucleus Models

Bertini, ISABEL, CEM2k : Nucleus is a continuous

  • medium. The nucleon densities are constant within

the certain zones. Bertini: Nucleus is divided as 3 concentric spheres with different densities. Pauli principle “strict”. CEM2k: Nucleus is divided as 7 concentric spheres with different densities. ISABEL: Nucleus is divided as 16 concentric spheres with different densities. Pauli principle “strict”. INCL4: Nucleus is a bundle of individual nucleons moving in a given potential.

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The spallation reaction is an interaction between a nucleon or a light nucleus of a few hundreds of MeV to a few GeV per nucleon and a target heavy nucleus. The INC model is generally considered to be valid when the incident particle has a sufficiently small de Broglie wavelength to interact with individual nucleons; this length should be smaller than the typical inter-nucleonic distances in the target nucleus.

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In the INC stage the incident particle strikes a nucleon in the target nucleus and produces secondary

  • particles. The primary and secondary particles can

interact with other nucleons or be absorbed. These successive collisions lead to the excitation of residual

  • nucleus. The cascade ends when all particles escape

the nucleus. The second stage called pre-equilibrium is an intermediate stage between cascade and evaporation- fission stage. The kinetic energies of the particles emitted in this stage higher than those of the particles emitted in the evaporation stage. The third stage is the de-excitation of the excited residual nucleus remaining via a process of evaporation – fission after cascade stage.

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Options offered in the MCNPX code based

Investigated Combinations Bertini/ABLA Bertini/Dresner CEM2k INCL4/ABLA INCL4/Dresner ISABEL/ABLA ISABEL/Dresner Bertini/Dresner is default option recommended by MCNPX.

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Scheme of the target-beam pipe system

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Beam particle type: Protons Beam energy: 1 GeV Beam current: 1 mA Beam Power: 1 MW Target: Pb-Bi eutectic Number of source particle histories per MCNPX calculation: 2.5x105

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Proton energy spectra in the beam window

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Proton energy spectra in the target

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Neutron energy spectra in the beam window

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Neutron energy spectra in the target

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Radial neutron flux in the target

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Axial neutron flux in the target

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Axial variation of the neutron flux on the target side face

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Neutron leakage spectra from the target bottom face

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Neutron leakage spectra from the target top face

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Angular neutron leakage spectra from the target top face

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Neutron leakage spectra from the target side face

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Angular neutron leakage spectra from the target side face

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Axial variation of the neutron flux in the beam window (n/(cm2.s.mA)

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Neutron Energy deposition in the beam window

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Proton energy deposition in the beam window

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Energy dependent total heating in the beam window

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Volume integrated neutron energy deposition in the target

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Energy dependent total heating in the target window

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Volume integrated proton energy deposition in the target

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Axial variation of the proton heating in the target

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Axial neutron energy deposition in the target

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Radial neutron energy deposition in the target

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Neutron, proton and pion multiplicities per incident proton on target

Physics model Neutron Proton Pion Bertini/ABLA 2.95E+01 8.25E-02 2.00E-03 Bertini/Dresner 2.82E+01 8.19E-02 1.96E-03 CEM2k 2.93E+01 6.49E-02 1.95E-03 INCL4/ABLA 2.70E+01 9.41E-02 2.69E-03 INCL4/Dresner 2.58E+01 9.31E-02 2.70E-03 ISABEL/ABLA 2.87E+01 8.49E-02 2.06E-03 ISABEL/Dresner 2.75E+01 8.52E-02 2.00E-03

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Differences in Neutron Multiplicity between Different Calculation Models

Physics Model I Physics Model II Deviation (%) * Bertini/DRESNER INCL4/DRESNER 8.51 Bertini/DRESNER ISABEL/DRESNER 2.48 Bertini/DRESNER Bertini/ABLA

  • 4.6

Bertini/ABLA INCL4/ABLA 8.5 (4.26) Bertini/ABLA ISABEL/ABLA 2.7 (1.77) ISABEL/DRESNER ISABEL/ABLA

  • 4.4

INCL4/DRESNER INCL4/ABLA

  • 4.7

ISABEL/DRESNER INCL4/DRESNER 6.2 ISABEL/ABLA INCL4/ABLA 6.0

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Differentiated Neutron Leakage out of Target for Selected Models [n/(s.mA)]

Physics model Bottom Top Side Total Bertini/ABLA 4.12E15 3.66E16 1.42E17 1.83E17 Bertini/Dresner 4.03E15 3.39E16 1.37E17 1.75E17 CEM2k 4.03E15 3.60E16 1.42E17 1.82E17 INCL4/ABLA 3.77E15 3.10E16 1.32E17 1.67E17 INCL4/Dresner 3.70E15 2.97E16 1.27E17 1.60E17 ISABEL/ABLA 4.16E15 3.55E16 1.39E17 1.79E17 ISABEL/Dresner 4.08E15 3.29E16 1.34E17 1.71E17

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Neutron induced proton production in the beam window

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Neutron induced deuterium production in the beam window

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Neutron induced tritium production in the beam window

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Neutron induced helium production in the beam window

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Neutron induced proton production in the target

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Neutron induced deuterium production in the target

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Neutron induced tritium production in the target

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Neutron induced helium production in the beam window

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CONCLUSIONS A systematic comparison

  • f

seven different calculation models in MCNPX has lead to different results in neutron multiplicity, neutron leakage and neutron spectra. These will have also direct impact on neutron heating and material damage in the beam window, furthermore

  • n

technical data and performance of ADS as a whole power plant with respect to plant power, transmutation, material damage, etc.

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The maximum value of the neutron flux in the target is observed on the axis ~ 10 cm below the beam window, where the maximum difference between 7 different models is ~ 15 %. The total neutron leakage out of the of the target calculated with the Bertini/ABLA is 1.83x1017 n/s, and is about 14 % higher than the value calculated by the INCL4/Dresner (1.60x1017 n/s).

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Bertini/ABLA calculates top, bottom and side neutron leakage fractions as 20 %, 2.3 %, 77.6 %

  • f the total leakage, respectively.

They become 18.6 %, 2.3 %, 79.4 % with INCL4/Dresner combination.

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MYRRHA: Major experimental Accelerator-Driven System (ADS)

IVFS Reacto r core

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Civilian nuclear power plants have produced nearly 1,700 tons of reactor-grade plutonium, of which about 274 tons have been separated and the rest is stored at reactor sites embedded in spent fuel Nuclear power plants in the European Union (~ 125 GW) produce yearly approximately 2500 tons of spent fuel, containing about 25 tons of plutonium and 3.5 tons of the “minor actinides (MA)” neptunium, americium, and curium and 3 tons of long-lived fission products Nuclear weapons nations have accumulated an estimated 250 tons of weapons-grade plutonium, most of it in the United States and Russia

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The composition of the reactor grade plutonium ISOTOPES

Reactor grade plutonium initial [%]

238Pu 239Pu 240Pu 241Pu 242Pu

1.0 62.0 24.0 8.0 5.0

IAEA, Potential Of Thorium Based Fuel Cycles to Constrain Plutonium and Reduce Long Lived Waste Toxicity, IAEA-TECDOC- 1349, International Atomic Energy Agency, Vienna, Austria, p.55, Table 3.3.6 (2003).

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Composition of MA in the spent fuel of a light water reactor

Pressurised-water reactor, fuel with plutonium recycle, 1000-MWel reactor, 80% capacity factor, 33 MW.D/kg, 32.5 % thermal efficiency, 150 days after discharge (Nuclear Chemical Engineering, p. 370, Table 8.5)

ISOTOPES Mass (kg/year) per unit PWR*

237Np 238Pu 239Pu 240Pu 241Pu 242Pu 241Am 242mAm 243Am 244Cm 245Cm

15.1 16.1 205 120 72.7 41.6 6 0.00793 21.8 15.6 1.74

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Subcritical core configuration

86 cm

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MYRRHA has a small active fuel length (65 cm) The spent fuel removal period is about 420 days

In-vessel fuel storage (IVFS)

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IVFS geometry

Each IVFS consists of 76 assembly positions

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Fission cross sections of 238U and 232Th

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Neutron/fission ()

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SLIDE 60
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Fission cross sections of 235U and 238U (< 10 MeV)

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Fission cross sections of 238U < 40 MeV

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Fission cross sections of 238U < 40 MeV

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Fission cross sections of 238U < 160 MeV

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Fission cross sections of 232Th < 40 MeV

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Fission cross sections of 240Pu < 30 MeV

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Fission cross sections of 240Pu (10 to 10000 eV)

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Fission cross sections of 240Pu < 30 MeV

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Fission cross sections of 242Pu < 20 MeV

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Fission cross sections of 242Pu (10 to 2000 eV)

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NUCLEAR PERFORMANCE of ACCELERATOR-DRIVEN SYSTEMS with URANIUM BLANKET

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Isotopes

235U 239Pu 233U

Spectrum Thermal Fast Thermal Fast Thermal Fast σf(barn) 582 1.81 743 1.76 531 2.79 σc(barn) 101 0.52 270 0.46 46 0.33 α=σc/σf 0.17 0.29 0.36 0.26 0.09 0.12 ν 2.42 2.43 2.87 2.94 2.49 2.53 η= νσf/σa 2.07 1.88 2.11 2.33 2.29 2.27 βeff(%) 0.650 0.210 0.276

Main nuclear properties of fission materials

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Energy dependence of uranium and thorium breeders

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M =1/(1-keff)

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Calculation Model

Bertini/ ABLA Bertini/ Dresner CEM2k CEM2k

238U

INCL4/ ABLA INCL4/ Dresner ISABEL/ ABLA ISABEL/ Dresner

(n/p) Total 88.00 82.16 91.96 80.24 83.67 65.95 88.02 81.54 Net (n,xn)/p 4.93 4.17 4.87 4.78 3.83 2.75 5.11 4.35 Net (*Σf)/p 41.22 36.72 42.49 30.82 37.26 27.05 41.64 36.97 Net Nuclear Interaction/p 40.41 41.26 44.59 44.63 42.56 36.16 41.27 40.23

238U(n,γ)239Pu

/p 86.75 80.99 90.65 80.24 82.48 65.01 86.78 80.39

235U(n,f)/p

5.24 4.88 5.48

  • 4.98

3.90 5.25 4.85

238U(n,f)/p

15.45 13.68 16.01 13.97 14.15 9.93 15.53 13.69 Total (n,f)/p 20.69 18.56 21.49 13.97 19.13 13.83 20.78 18.54 FissionHeatin g (GeV/p) 3.76 3.37 3.90 2.53 3.47 2.51 3.77 3.37 Total Heating (GeV/p) 5.27 4.94 5.45 4.03 5.03 3.47 5.30 4.93 M 5.27 4.94 5.45 4.03 5.03 3.47 5.30 4.93 k∞ 0.810 0.798 0.816 0.752 0.801 0.712 0.811 0.797

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Energy (MeV) Neutron Flux [n/cm2.sec] Fraction 0-1 2.32E-03 0.925 1-10 1.72E-04 0.069 10-20 6.57E-06 0.003 20-50 4.54E-06 0.002 50-100 2.15E-06 0.001 100-1000 2.44E-06 0.001 Total (0-1000) 2.50E-03 1.0

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Natural uranium 100 % 238U (fully depleted uranium) Energy (MeV) (n,f)/p Fraction (n,f)/p Fraction 0-1 5.379 0.250 0.193 0.014 1-10 13.890 0.646 11.565 0.828 10-20 1.490 0.069 1.476 0.106 20-1000 0.730 0.034 0.739 0.053 Total (0- 1000) 21.489 1.0 13.973 1.0

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NUCLEAR PERFORMANCE of ACCELERATOR-DRIVEN SYSTEMS with THORIUM BLANKET

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R = 100 cma R = 100 cmb R = 40 cmb R = 100 cma R = 100 cmb R = 40 cmb Energy (MeV) Flux [n/cm2.sec] Fraction Flux [n/cm2.sec] Fraction Flux [n/cm2.sec] Fraction 0-1 1.812E-03 0.912 1.759E-03 0.911 1.280E-02 0.861 1-10 1.515E-04 0.076 1.501E-04 0.078 1.800E-03 0.121 10-20 8.775E-06 0.004 8.732E-06 0.005 1.113E-04 0.007 20-50 6.824E-06 0.003 6.738E-06 0.003 8.017E-05 0.005 50-100 3.429E-06 0.002 3.401E-06 0.002 3.887E-05 0.003 100- 1000 3.942E-06 0.002 3.859E-06 0.002 4.318E-05 0.003 0-1000 1.987E-03 1.0 1.932E-03 1.0 1.487E-02 1.0

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R = 100 cma R = 100 cmb R = 40 cmb R = 100 cma R = 100 cmb R = 40 cmb Energy (MeV)

232Th(n,f)/p Fraction 232Th(n,f)/p Fraction 232Th(n,f)/p

Fraction

0-1 0.0068 0.0022 0.0067 0.0022 0.0045 0.0019 1-10 1.9016 0.6071 1.8881 0.6076 1.5015 0.6136 10-20 0.4295 0.1371 0.4275 0.1376 0.3472 0.1419 20-50 0.6727 0.2148 0.6643 0.2138 0.5051 0.2064 50-100 0.1218 0.0389 0.1207 0.0388 0.0885 0.0362 0-1000 3.1324 1.0 3.1072 1.0 2.4468 1.0

a) Infinite dimension; b) Finite dimension

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R = 100 cma R = 100 cmb R = 40 cmb R = 100 cma R = 100 cmb R = 40 cmb Energy (MeV)

232Th(n,)/

p Fraction

232Th(n,)

/p Fractio n

232Th(n,γ)

/p Fraction 0-1

51.602 0.9745 49.816 0.9738 21.26 0.9551

1-10

1.3513 0.0255 1.337 0.0261 1.00 0.0449

10-20

9.83E-04 1.86E-05 9.78E-04 1.91E-05 8.03E-04 3.61E-05

20-50

5.09E-05 9.61E-07 5.03E-05 9.83E-07 3.87E-05 1.74E-06

50-100

4.09E-07 7.73E-09 4.06E-07 7.93E-09 2.97E-07 1.34E-08

0-1000

52.954 1.0 51.155 1.0 22.261 1.0

a) Infinite dimension; b) Finite dimension

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Neutron and -particles spectrum at a plasma temperature of 70 keV

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FINAL CONCLUSIONS

A real assembly will contain coolant and structural materials. Hence, the performance will be lower.

 Final blanket dimensions will lead neutron

leakage, which can be suppressed to a great degree with appropriate neutron reflectors.

 Utilization of natural breeder materials 232Th

and 238U in ADS allows only a modest energy multiplication.

 On the other hand, ADS has high fissile fuel

breeding capability due to abundant neutron population through spallation.

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