Testing shields in the Argonne National Laboratory fuel conditioning facility support areas

Area of Science:

• Nuclear Engineering
• Radiation Protection
• Materials Science

Background:

• The Fuel Conditioning Facility at Idaho National Engineering Laboratory requires robust shielding for radioactive material handling.
• Operational demands necessitate rigorous testing of shielding effectiveness for decontamination and waste management areas.

Purpose of the Study:

• To evaluate the efficacy of existing reinforced concrete, steel, and lead shot shielding.
• To identify design flaws and construction deficiencies in shielded areas.
• To ensure radiation dose rates comply with regulatory limits for personnel and occupied spaces.

Main Methods:

• Utilized iridium-192 radiography sources (0.44 TBq and 0.89 TBq) to simulate operational radiation fields.
• Conducted measurements to assess gamma ray deep dose equivalents and dose rates.
• Developed specialized measurement procedures to minimize radiation exposure during testing.

Main Results:

• Existing shields are adequate for limiting deep dose equivalents to 10 mSv/y for facility personnel.
• Several shielding modifications were identified as necessary.
• Attenuations require improvement to maintain dose rates below 5 microSv/h in normally occupied areas.

Conclusions:

• The tested shielding provides a foundational level of protection but requires enhancements.
• Specific modifications are crucial for achieving optimal radiation protection standards.
• The study underscores the importance of continuous assessment and improvement in nuclear facility shielding.