M-PRISM research

Optimizing radioisotope production at MURR

Development and Validation of an OpenMC/Fission-Matrix Methodology for Real-Time Prediction and Optimization of Target Irradiation and Isotope Yields

Our OpenMC model of MURR agrees with MCNP to within 50 pcm in all 12 core and blade states.

The University of Missouri Research Reactor (MURR) runs about 6.5 days a week and must refuel and place targets within about 12 hours. That is too short for high-fidelity transport, so irradiation planning relies on spreadsheet methods.

The aim is real-time prediction and optimization of target irradiation and isotope yields. The planned method precomputes fission-matrix and detector-response data with OpenMC. A machine-learning inverse solver searches these data for loadings that meet an irradiation goal. The fission-matrix physics engine scores every candidate.

Undergraduate Ethan Mohr built the first piece: an OpenMC model of MURR verified against MCNP 6.3.1, with blade worths within 0.25%. Validation against MURR measurements is next.

  • Isotope production
  • Fission matrix
  • OpenMC
  • Verification and validation
OpenMC model of the MURR core at mid-plane: eight fuel elements, each of 24 curved fuel plates, arranged around the central flux trap.
OpenMC model of the MURR core at mid-plane: eight fuel elements, each of 24 curved fuel plates, arranged around the central flux trap. Select to enlarge.
Difference in k-effective between the OpenMC and MCNP models of MURR for 12 cases: burned core (equilibrium xenon) and fresh core, each with six control-blade states. All 12 differences lie inside the ±50 pcm goal.
Difference in k-effective between the OpenMC and MCNP models of MURR for 12 cases: burned core (equilibrium xenon) and fresh core, each with six control-blade states. All 12 differences lie inside the ±50 pcm goal. Select to enlarge.

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