Need for enrichment of lutetium isotope and design of a laser based separator module.

Lutetium-177 radio-pharmaceutical has become an important theranostic candidate in cancer treatment. Its availability from bench-to-bed requires strategic implementation of isotope-enrichment, neutron-irradiation and radio-chemical techniques. In this paper, the need for enrichment of lutetium-176 is emphasized by estimating specific activity of lutetium-177 as a function of enrichment percentage for typical neutron flux available at Dhruva reactor, India. A novel Atomic Vapour Laser Isotope Separation (AVLIS) module for lutetium-176 enrichment is designed to meet the above requirement. The paper documents its characteristics and production estimates. The design is carried out after critical assessment and evaluation of available AVLIS-infrastructure in the country. Outline of lutetium-177 enrichment, capable of producing non-carrier-added lutetium is also provided. This work concludes that India has taken a step forward towards self-reliance (Atmanirbhar Bharat) in securing the supply chain of lutetium-177. • Estimation of specific activity of 177Lu using Bateman's approach. • Assessment of enrichment technologies for neutron flux of Dhruva reactor, India. • Selection of AVLIS for 176Lu enrichment after reviewing its infrastructure in India. • Design of AVLIS-module to achieve useable amount and desired enrichment of 176Lu. • Outline for enrichment of 177Lu to produce carrier-free 177Lu. [ABSTRACT FROM AUTHOR]