Ma and llfp transmutation performance assessment in the myrrha experimental ads
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MA and LLFP Transmutation Performance Assessment in the MYRRHA eXperimental ADS. E. Malambu , W. Haeck, V. Sobolev and H. Aït Abderrahim SCK·CEN, Boeretang 200, Mol, Belgium. P&T: 8th IEM, Las Vegas, Nevada, USA. November 9-11, 2004. Contents. Introduction: MYRRHA-XADS

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Ma and llfp transmutation performance assessment in the myrrha experimental ads

MA and LLFP Transmutation Performance Assessment in the MYRRHA eXperimental ADS

E. Malambu, W. Haeck, V. Sobolev

and H. Aït Abderrahim

SCK·CEN, Boeretang 200, Mol, Belgium

P&T: 8th IEM,

Las Vegas, Nevada, USA

November 9-11, 2004


Contents
Contents MYRRHA eXperimental ADS

  • Introduction: MYRRHA-XADS

  • Typical core configuration for MA and LLFP transmutation studies

  • MA and LLFP targets loading

  • Computational tools

  • Geometrical model features

  • Target irradiation conditions

  • Preliminary results

  • Conclusions


1 introduction
1. Introduction MYRRHA eXperimental ADS

  • Since 1998, the Belgian nuclear research Centre, SCK·CEN, is developing the MYRRHA ADS project.

  • In 2004, SCK•CEN is finalizing the pre-design phase of MYRRHA.

  • In the framework of the EC FP6 IP-EUROTRANS project, SCK•CEN is willing to adapt the design options of MYRRHA to fit out the objectives of the ETD/XT-ADS project (experimental demonstration of the technological feasibility of Transmutation in an ADS).




4 computational tools
4. Computational studiestools

  • MCNPX 2.5.e code used to:

    • Define the sub-critical core configuration such as:

      • Keff-value close to 0.95

      • Total power close 50 MWth

    • Calculate neutron fluxes and spectra at each burn-up step through the ALEPH code flowchart

  • Libraries: JEF2.2 (MCB) combined to LA150n for Pb, Bi and steel elements); LA150h for protons.

  • ALEPH code (coupling MCNPX and ORIGEN2.2) to carry out the MA evolution calculation


4 computational tools cont d aleph

MCNPX studies

calculate multigroup spectra

ORIGEN LIBRARY

use data directly from ENDF files preprocessed by NJOY 99.90

ORIGEN 2.2

burn up calculation

NEW MCNP(X) INPUT

update densities and composition

4. Computational tools(cont’d)ALEPH

MCNPX calculates the spectrum in cells to be burned in an arbitrary group structure

The spectra are used to calculate reaction rates outside MCNPX using data read directly from ENDF files

The updated library is used to calculate new material compositions and densities

This entire process is repeated until the entire burn up history is calculated


5 geometrical model features myrrha model for mcnpx calculations
5. studiesGeometrical model features:MYRRHA MODEL for MCNPX calculations


5 geometrical model features cont d modelled details of various assemblies
5. studiesGeometrical model features (cont’d):Modelled details of various assemblies


6 irradiation conditions
6. Irradiation conditions studies

  • Irradiation history:

    • One-year operational period 3 cycles

    • Cycle time-span 90 (EFP) days

    • Shutdown between cycles 30 days

  • Neutron flux :

    • Constant level assumed over 30 days sub-cycles

    • Cycle-and-volume averaged neutron flux

      • MA targets in channel A: 3.17·1015 n/cm²s

      • MA targets in channel D: 2.78·1015 n/cm²s

      • 99Tc targets : 1.08·1015 n/cm²s


7 preliminary results core physics static parameters
7. Preliminary results: studiesCore physics static parameters


7 preliminary results cont d neutron spectra in mox fuel and ma assemblies
7. studiesPreliminary results (cont’d)Neutron spectra in MOX fuel and MA assemblies


7 preliminary results cont d neutron spectrum in 99 tc target
7. studiesPreliminary results (cont’d)Neutron spectrum in 99Tc target


7 preliminary results cont d 99 tc incineration

99 studiesTc

Irradiation history

7. Preliminary results (cont’d)99Tc incineration

  • Mass incinerated: 431 grams (1.75% of initial mass)

  • Burnout half-life (T1/2=Ln(2)/saf):

    • 13.9 yrs vs T1/2 = 2.11 x 105 yrs for natural decay


7 preliminary results cont d mass evolution of am pu and cm in ma targets
7. studiesPreliminary results (cont’d)Mass evolution of Am, Pu and Cm in MA targets


7 preliminary results cont d time evolution of am mass
7. studiesPreliminary results (cont’d)Time-evolution of Am mass


7 preliminary results cont d time evolution of pu mass
7. studiesPreliminary results (cont’d)Time-evolution of Pu mass


7 preliminary results cont d time evolution of cm mass
7. studiesPreliminary results (cont’d)Time-evolution of Cm mass


8 conclusions
8 studies. CONCLUSIONS

  • The fast spectrum available in the MYRRHA sub-critical core is very efficient for the transmutation of (Pu, Am) targets due to a better fission-to-absorption ratio than in fast reactors

  • The incineration of Cm pre-requires a Partitioning step to separate Cm and Am

  • The incineration of long-lived fission products, such as the 99Tc, in a resonance capture region is demonstrated.

  • Further studies are underway to enhance the epithermal tail of the neutron spectrum by optimizing the target design and choosing more appropriate spectrum softening materials.


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