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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
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.
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.
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.