Study on calculation of optimal irradiation time for Iodine-125 production at Dalat Nuclear Reactor

Authors

  • Thi Thu Hien Doan
  • The Nghia Nguyen
  • Thanh Quang Vu

Keywords:

Iodine-125 production, irradiation time, thermal neutron, xenon target.

Abstract

Iodine-125 is an important radiopharmaceutical used in radiation immunity diagnostic kits, thyroid radiography, prostate cancer treatment, and brachytherapy to treat some malignant, brain tumors. Iodine-125 is produced from Xenon gas irradiated by thermal neutron in a nuclear reactor. At present, Iodine-125 has not yet been produced in Vietnam. Optimising the irradiation time is the first important step to carry out a successful production. In this work, we have programmed and calculated the optimal irradiation time for production of Iodine-125 from the natural Xenon and the enriched Xenon target irradiated by the thermal neutron of Dalat Nuclear Reactor.

 

Classification number

3.2

Author Biographies

Thi Thu Hien Doan

Vietnam Atomic Energy Institute

The Nghia Nguyen

University of Science, VNU

Thanh Quang Vu

108 Military Cental Hospital

Downloads

Published

2019-09-25

Received: 6 May 2019; accepted: 28 June 2019

How to Cite

Doan, T. T. H., Nguyen, T. N., & Vu, T. Q. (2019). Study on calculation of optimal irradiation time for Iodine-125 production at Dalat Nuclear Reactor. Version B of Vietnam Journal of Science and Technology, 61(9). Retrieved from https://b.vjst.vn/index.php/ban_b/article/view/138

Issue

Section

Medical and Pharmacological Sciences