Spectrometric analysis and internal dose assessment in lung counting for reactor-grade Pu compounds

Area of Science:

• Nuclear Physics
• Radiological Protection
• Occupational Health

Background:

• Internal plutonium (Pu) contamination is a critical risk in nuclear fuel cycles.
• Lung counting using 241Am gamma rays is standard but has limitations for Pu isotopes.
• Severe exposure scenarios require refined monitoring and dose assessment protocols.

Purpose of the Study:

• To examine challenges in lung counting and dose assessment for Pu isotopes.
• To develop improved procedures for severe internal exposure incidents.
• To support emergency response in nuclear facilities.

Main Methods:

• Analysis of spectral peaks in lung counting.
• Assessment of minimum detectable activity for Pu isotopes with 241Am interference.
• Evaluation of minimum assessable dose based on Pu isotopic composition.

Main Results:

• Identified complex spectral analysis as a key challenge.
• Quantified increased minimum detectable activity for Pu due to 241Am.
• Established methods for dose evaluation considering specific Pu isotopes (238Pu-242Pu).

Conclusions:

• Refined lung counting and dose assessment procedures are essential for severe Pu exposure.
• Improved methods enhance accuracy and support emergency response capabilities.
• Addressing challenges like 241Am interference is crucial for effective radiological protection.