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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. Introduction: MYRRHA-XADS

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MA and LLFP Transmutation Performance Assessment in the MYRRHA eXperimental ADS

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  1. 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

  2. Contents • 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

  3. 1. Introduction • 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. 2.Typical core configuration for MA and LLFP transmutation studies

  5. 3. MA and LLFP targets composition

  6. 4. Computational tools • 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

  7. MCNPX 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

  8. 5. Geometrical model features:MYRRHA MODEL for MCNPX calculations

  9. 5. Geometrical model features (cont’d):Modelled details of various assemblies

  10. 6. Irradiation conditions • 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

  11. 7. Preliminary results:Core physics static parameters

  12. 7. Preliminary results (cont’d)Neutron spectra in MOX fuel and MA assemblies

  13. 7. Preliminary results (cont’d)Neutron spectrum in 99Tc target

  14. 99Tc 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

  15. 7. Preliminary results (cont’d)Mass evolution of Am, Pu and Cm in MA targets

  16. 7. Preliminary results (cont’d)Time-evolution of Am mass

  17. 7. Preliminary results (cont’d)Time-evolution of Pu mass

  18. 7. Preliminary results (cont’d)Time-evolution of Cm mass

  19. 8. 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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