Published 2022 | Version v1
Book

Validation of 131I yields from fission and irradiation of 130Te

  • 1. Reactor Physics and Nuclear Engineering Section, Research Reactor Services Division, Reactor Group, Bhabha Atomic Research Centre, Mumbai, 400085 (India)

Description

131I, a radioactive (T1/2 ~8 days) isotope of element iodine, is an important isotope due to its wide applications especially in the field of healthcare. It is used in medical therapies for diagnosis as well as treatment, especially of ailments related to thyroid. It is also used as an industrial tracer. 131I is produced in nuclear reactors by neutron irradiation of 130Te. 131I also appears as a product in fission of heavy nuclides. In order to get the maximum specific activity of 131I, it is required to have a suitably optimized irradiation scheme for the specific reactor system and an efficient extraction methodology to deduce maximum 131I from irradiated samples. The optimization of activation and decay procedures requires an accurate estimation of the yield of 131I as a function of time during the generation process and subsequent radioactive cooling. Unfortunately, the literature contains inconsistent and erroneous results of the 131I yield as a function of neutron fluence, target mass, irradiation time and post-irradiation decay. We have developed an analytical model to calculate the yield of 131I produced either in fission or by irradiation of 130Te as a function of irradiation time, cooling time, sample mass and neutron flux. Our model is based on general and mathematically exact solution of governing rate equations and does not build upon the approximations on which conventional analytical methods are based. We have tested our model by comparing its results with those from other studies and found it satisfactory. Estimation of activity calls for a careful and judicious selection of cross-section data as they are found to vary widely across different studies. To estimate the activity for Dhruva, we calculated the flux depression factor and microscopic cross-section using the neutronic code DRAGON by simulating the actual target sample geometry and properties in Dhruva fuel matrix. Flux depression factor was also estimated by a diffusion theory-based model and was found close to that obtained from DRAGON. We have used our model with thus obtained cross-section and flux depression factor to estimate 131I activity produced in Dhruva at different tray rod locations and found them in agreement with the measured values. (author)

Part of:
Proceedings of the DAE-BRNS two-day theme meeting on strategic planning for enhancing research reactor utilization: book of abstracts

Additional details

Publishing Information

Publisher
Bhabha Atomic Research Centre
Imprint Place
Mumbai (India)
Imprint Title
Proceedings of the DAE-BRNS two-day theme meeting on strategic planning for enhancing research reactor utilization: book of abstracts
Imprint Pagination
264 p.
Journal Page Range
p. 30

Conference

Title
DAE-BRNS two-day theme meeting on strategic planning for enhancing research reactor utilization
Acronym
RRU-2022
Dates
6-7 May 2022
Place
Mumbai (India)

Optional Information