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Published: 2021-09-01
Abstract Views: 160
Views PDF: 82
DOI: https://doi.org/10.53747/jnst.v9i3.39
Issue
Vol. 9 No. 3 (2019)
Section
Articles
How to Cite
Nguyen Kien, C., Huynh Ton , N., Le Vinh, V., Luong Ba, V., Pham Quang, H., Tran Quoc, D., & Bui Van, C. (2021). Calculation Results for Enhancing Ability of I-131 Radioisotope Production Using Tellurium Dioxide Target on the Dalat Nuclear Research Reactor. Nuclear Science and Technology, 9(3). https://doi.org/10.53747/jnst.v9i3.39

Calculation Results for Enhancing Ability of I-131 Radioisotope Production Using Tellurium Dioxide Target on the Dalat Nuclear Research Reactor

Nguyen Kien Cuong1, Huynh Ton Nghiem1, Le Vinh Vinh1, Luong Ba Vien1, Pham Quang Huy, Tran Quoc Duong1, Bui Van Cuong1
1 Dalat Nuclear Research Institute, Vietnam Atomic Energy Institute

Main Article Content

Abstract

The paper presents the calculation results in re-design of neutron trap of the Dalat Nuclear Research Reactor (DNRR) for I-131 radioisotope production using TeO2 target. The new design permits for loading more TeO2 capsules from 9 to 12, 15 and 18 in the neutron trap. The enhancement of radioisotope production was implemented by re-arrangement of the neutron trap without changing the dimension or geometry of irradiation capsules. By using neutronics computer code as MCNP6, the obtained calculation results of I-131 activity in 6 investigated cases showed that the new design by the re-arrangement of the neutron trap can be used effectively for radioisotope production with thermal neutron flux in average range from 5.3×1012 to 1×1013 n/cm2.s and the total activity of I-131 isotope was increased from about 19.2% to 38.8% comparing with the original design using 9 capsules. The negative reactivity insertion was from 0.60 βeff to 0.96 βeff when loading capsules that also met the safety requirements of operational conditions of the DNRR.

Article Details

Keywords

The DNRR, Radioisotope Production, TeO2, I-131, MCNP6 code

References

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