Attenu OpenMC

Monte-Carlo photon transport & energy spectrum solver

Idle

Dose Rate H*(10)

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µSv/h [H*(10)]
Ref: ICRP 74

Calculation Uncertainty

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Relative Error (1σ)

Detector photons number (gamma)

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photons (simulated)

Source Photon Rate

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photons / s

Run Information Summary

  • World Box Side: --
  • Screen Height/Width: --
  • Source Energy: --
  • Target Particles: --
  • Detector Radius (10% D): --

H*(10) Dose Rate — Comparison

Monte Carlo (OpenMC)
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µSv/h [H*(10)] — ICRP 74
σ: --
Lines used: --
Analytical (Point-Kernel)
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µSv/h [H*(10)] — ICRP 74
Buildup: --
All lines · With buildup

Gamma Lines — Deterministic Pre-filter

Nuclide Energy (MeV) Emission (γ/s) Det. DED (µSv/h) Contribution (%) MC?

Inventory after Decay & Daughter Nuclides

Nuclide Status Half-life (T½) Initial Quantity Decayed Quantity Proportion (%)

Photon Energy Spectrum at Detector

Energy Response Function Dose rate H*(10) (pSv·cm²) — ICRP 74 Reference curve + gamma line contributions