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Validation of the MCNP6 code for SFR shielding design analysis.

Tuan Quoc Tran1, Sanggeol Jeong1, Khang Nhat Hoang Nguyen1

  • 1Department of Nuclear Engineering, Ulsan National Institute of Science and Technology 50 UNIST-gil, Ulsan 44919, Republic of Korea.

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This study assesses the uncertainty of MCNP6 code for sodium-cooled fast reactor (SFR) shielding design. Analysis of four SFR benchmarks validates MCNP6 performance for radiation safety assessments.

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Area of Science:

  • Nuclear Engineering
  • Radiation Shielding Physics

Background:

  • Shielding analysis is critical for ensuring radiation safety in sodium-cooled fast reactor (SFR) designs.
  • Monte Carlo (MC) modeling, while powerful, introduces significant uncertainties in shielding calculations.
  • Accurate shielding design is paramount for the safety and viability of advanced reactor concepts like SFRs.

Purpose of the Study:

  • To evaluate the uncertainty of the MCNP6 Monte Carlo code for sodium-cooled fast reactor (SFR) shielding design.
  • To assess the performance of MCNP6 by analyzing selected SFR shielding benchmarks.
  • To provide validated MCNP6 models for radiological protection and shielding design of the Korean Prototype Gen-IV SFR.

Main Methods:

  • Utilized the MCNP6 Monte Carlo code for simulations.
  • Employed the weight window variance-reduction technique to improve computational efficiency.
  • Used the ENDF/B-VII.1 neutron data library for nuclear cross-section data.
  • Analyzed four specific SFR shielding benchmarks: JANUS Phase VIII, SDT12, EURAC_Na, and HARMO_Na.

Main Results:

  • Presented the results of MCNP6 simulations for the selected SFR shielding benchmarks.
  • Validated the MCNP6 models against available experimental measurement data.
  • Quantified the uncertainties associated with MCNP6 in SFR shielding design scenarios.

Conclusions:

  • The MCNP6 code, when utilized with the weight window variance-reduction technique and ENDF/B-VII.1 library, provides reliable predictions for SFR shielding design.
  • Validation against benchmark data confirms the suitability of MCNP6 for assessing radiation safety in SFRs.
  • The findings support the radiological protection and shielding design of the Korean Prototype Gen-IV SFR.