ScholarGate
アシスタント

手法を比較

選択した手法を並べて確認できます。異なる行はハイライト表示されます。

放射線線量評価×モンテカルロ中性子・粒子輸送×
分野原子核物理学原子核物理学
系統Process / pipelineProcess / pipeline
提唱年19281949
提唱者International Commission on Radiological Protection (ICRP)Nicholas Metropolis, Stanislaw Ulam
種類computational health assessment pipelineprobabilistic computational method
原典International Commission on Radiological Protection (2007). The 2007 Recommendations of the ICRP. Publication 103. Annals of the ICRP, 37(2–4). link ↗Metropolis, N., & Ulam, S. (1949). The Monte Carlo Method. Journal of the American Statistical Association, 44(247), 335–341. DOI ↗
別名dose calculation, exposure assessment, radiation hazard evaluationMonte Carlo simulation, stochastic transport, particle history method
関連55
概要Radiation dose assessment is a systematic evaluation of human exposure to ionizing radiation from external or internal sources, formalized by the International Commission on Radiological Protection (ICRP) in the late 20th century. It combines radiation transport calculations with biological effect models to quantify absorbed dose, equivalent dose, and effective dose for worker safety and public health protection.Monte Carlo neutron and particle transport is a stochastic simulation method that tracks individual particle histories through matter, developed by Metropolis and Ulam in 1949 during the Manhattan Project. By sampling random numbers to determine collision locations, energy transfers, and scattering angles, it produces unbiased estimates of reaction rates, flux distributions, and detector responses without discretizing angle or energy variables.
ScholarGateデータセット
  1. v1
  2. 2 出典
  3. PUBLISHED
  1. v1
  2. 2 出典
  3. PUBLISHED

検索へ スライドをダウンロード

ScholarGate手法を比較: Radiation Dose Assessment · Monte Carlo Neutron & Particle Transport. 2026-06-20に以下より取得 https://scholargate.app/ja/compare