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Feasibility studies for assessing internal exposure to 233U.

D J Mehta1, R C Sharma, A Ramanujam

  • 1Internal Dosimetry Division, Bhabha Atomic Research Centre, Mumbai-400 085, India.

Radiation Protection Dosimetry
|October 7, 2003
PubMed
Summary

This study explores methods for assessing internal exposure to uranium-233 (233U) and thorium-232 (232Th) in the nuclear fuel cycle. It evaluates urine bioassay, in vivo counting, and exhaled thoron gas measurement for worker safety.

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Area of Science:

  • Nuclear Chemistry and Health Physics
  • Occupational Health and Safety in Nuclear Facilities

Background:

  • The 232Th-233U fuel cycle presents potential internal occupational exposure risks primarily through inhalation of 232Th, 233U, and their compounds.
  • Existing methods for assessing internal exposure to 232Th are established, but standardized methods for 233U and combined 233U + 232Th exposure are lacking.

Purpose of the Study:

  • To conduct feasibility studies for assessing internal exposure to 233U and 232Th.
  • To evaluate the effectiveness of different bioassay techniques for monitoring workers in the 232Th-233U fuel cycle.

Main Methods:

  • Investigated three primary methods for internal exposure assessment: urine bioassay, in vivo counting, and measurement of thoron gas in exhaled breath.
  • Detailed descriptions of the study's methodologies are provided.

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Main Results:

  • The paper presents and discusses the results obtained from the feasibility studies.
  • Findings contribute to the development of standardized assessment protocols for 233U and 232Th internal exposure.

Conclusions:

  • The feasibility studies demonstrate viable methods for assessing internal exposure to 233U and 232Th.
  • These findings are crucial for enhancing occupational health and safety measures in nuclear facilities utilizing the 232Th-233U fuel cycle.