Validation of 131I yields from fission and irradiation of 130Te
Creators
- 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)
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)
INIS
- Country of Publication
- India
- Country of Input or Organization
- India
- INIS RN
- 53113492
- Subject category
- S73: NUCLEAR PHYSICS AND RADIATION PHYSICS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- FISSION; FISSION YIELD; HALF-LIFE; IODINE 131; TELLURIUM 130 TARGET; TRACER TECHNIQUES
- Descriptors DEC
- BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; DAYS LIVING RADIOISOTOPES; INTERMEDIATE MASS NUCLEI; IODINE ISOTOPES; ISOTOPE APPLICATIONS; ISOTOPES; NUCLEAR REACTION YIELD; NUCLEAR REACTIONS; NUCLEI; ODD-EVEN NUCLEI; RADIOISOTOPES; TARGETS; YIELDS