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All radioactive nuclides emit high-energy particles or electromagnetic waves. When this radiation encounters living cells, it can cause heating, break chemical bonds, or ionize molecules. The most serious biological damage results when these radioactive emissions fragment or ionize molecules. For example, α and β particles emitted from nuclear decay reactions possess much higher energies than ordinary chemical bond energies. When these particles strike and penetrate matter, they...
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EVALUATION OF INTERNAL EXPOSURE TO RADIOACTIVE AEROSOL GENERATED FROM PLASMA MELTING SYSTEM USING THE BIDAS CODE.

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Workers at nuclear power plants (NPPs) face internal radiation exposure risks from radioactive aerosols. This study estimated worker doses using ICRP guidelines and actual site data, finding exposures below the 20 mSv/yr annual limit.

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Area of Science:

  • Radiological Protection
  • Nuclear Engineering
  • Occupational Health

Background:

  • Nuclear Power Plant (NPP) decommissioning generates radioactive aerosols, posing inhalation risks and internal radiation exposure to workers.
  • Internal exposure is challenging to measure directly, necessitating accurate dose assessment methods for occupational safety.
  • The International Commission on Radiological Protection (ICRP) provides recommended values for estimating internal exposure doses when direct measurements are difficult.

Purpose of the Study:

  • To estimate the internal radiation exposure dose for workers involved in NPP decommissioning.
  • To assess the effectiveness of using ICRP-recommended parameters for internal dose estimation in a real-world scenario.
  • To ensure worker safety by verifying that estimated doses remain below regulatory limits.

Main Methods:

  • Utilized ICRP-recommended particle size (5 μm) and considered both heavy and light respiratory rates for dose calculation.
  • Applied actual data on nuclides and concentrations from radioactive aerosols sampled at the Kozloduy NPP melting facility in Bulgaria.
  • Employed established methods for internal exposure dose estimation based on inhaled radioactive material.

Main Results:

  • Estimated internal exposure doses for workers were found to be below the maximum annual permissible limit of 20 mSv/yr.
  • The study demonstrated the feasibility of estimating internal exposure doses using site-specific data and ICRP guidelines.
  • No worker exceeded the regulatory annual dose limit, indicating effective safety measures or conservative estimation.

Conclusions:

  • The estimated internal radiation doses for workers at the Kozloduy NPP decommissioning site are within safe occupational limits.
  • The methodology provides a reliable approach for assessing internal exposure in scenarios where direct measurement is impractical.
  • This study reinforces the importance of adhering to ICRP recommendations and utilizing site-specific data for robust radiological protection of nuclear workers.