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Published on: December 14, 2017
A shielding design for an accelerator-based neutron source for boron neutron capture therapy
A E Hawk1, T E Blue, J E Woollard
1Nuclear Engineering Program, The Ohio State University, 206 West, 18th Avenue, Columbus, Oh 43210-1189, USA.
Summary
This study compares shielded and unshielded moderator assemblies for accelerator-based neutron sources in boron neutron capture therapy (BNCT). Shielded designs offer superior radiation protection for personnel, reducing material needs.
Area of Science:
- Nuclear Engineering
- Medical Physics
- Radiation Oncology
Background:
- Boron Neutron Capture Therapy (BNCT) requires a high-quality neutron field.
- Accelerator-Based Neutron Sources (ABNS) are being developed for BNCT applications.
- Current ABNS designs involve complex systems including accelerators, targets, and moderator assemblies.
Purpose of the Study:
- To evaluate the efficacy of a shielded moderator assembly design for BNCT.
- To compare material requirements for shielded versus unshielded moderator assemblies.
- To demonstrate the safety advantages of shielded designs for radiation personnel.
Main Methods:
- Design and analysis of a shielded moderator assembly for an ABNS.
- Comparison of radiation shielding properties between shielded and unshielded designs.
- Assessment of material requirements for personnel protection.
Main Results:
- The shielded moderator assembly design significantly enhances radiation protection for personnel outside the treatment room.
- Shielded designs require optimized material selection for effective neutron moderation and gamma shielding.
- The study quantifies the reduction in radiation exposure achievable with a shielded design.
Conclusions:
- Shielded moderator assemblies are advantageous for BNCT ABNS, providing improved safety for radiation workers.
- Careful material selection is crucial for optimizing shielding performance and minimizing material usage.
- This research supports the development of safer and more efficient BNCT facilities.
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