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Full core analysis of IRIS reactor by using MCNPX.

E A Amin1, I I Bashter2, Nabil M Hassan2

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Summary

Neutronic analysis of the IRIS reactor using MCNPX code was performed. Results for criticality and power distribution were validated against multiple codes, showing good agreement.

Keywords:
Axial powerBenchmark 44IRIS CoreMCNPX codeNuclear peaking factorRadial power

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Area of Science:

  • Nuclear Engineering
  • Computational Physics

Background:

  • Accurate neutronic analysis is crucial for nuclear reactor safety and efficiency.
  • The International Reactor Innovative and Secure (IRIS) reactor design requires detailed neutronic assessment.
  • Verification of computational methods against established codes is essential for reliable simulations.

Purpose of the Study:

  • To conduct a comprehensive neutronic analysis of a fresh-fueled IRIS reactor using the MCNPX code.
  • To validate MCNPX results by comparing criticality and power distribution calculations with established codes.
  • To investigate the impact of Boron-10 enrichment on the effective multiplication factor (k-eff) using WIMS-D5.

Main Methods:

  • Neutronic analysis utilizing the MCNPX Monte Carlo code.
  • Criticality calculations, including effective multiplication factor (k-eff) determination.
  • Assessment of radial and axial power distributions, nuclear peaking factor, and axial offset.
  • Comparison of MCNPX results with HELIOS/NESTLE, CASMO/SIMULATE, CORD-2, and SAS2H/KENO-V.
  • Simulation of Boron-10 enrichment effects using WIMS-D5 code.

Main Results:

  • The MCNPX code yielded an effective multiplication factor (k-eff) value closely matching that from modified CORD-2 calculations.
  • Radial and axial power distributions calculated by MCNPX showed good agreement with published SAS2H/KENO-V results.
  • WIMS-D5 analysis indicated the effect of Boron-10 enrichment on the fuel pin's k-eff at various burnup stages, consistent with HELIOS code findings.

Conclusions:

  • MCNPX is a reliable tool for neutronic analysis of the IRIS reactor, with results validated against multiple established codes.
  • The study provides a benchmark for future neutronic assessments of the IRIS reactor design.
  • Understanding the impact of neutron absorbers like Boron-10 is vital for reactor core management and safety.