Article Sidebar

PDF
Published: 2019-09-15
Abstract Views: 109
Views PDF: 37
DOI: https://doi.org/10.53747/jnst.v9i3.38
Issue
Vol. 9 No. 3 (2019)
Section
Articles
How to Cite
Peng, H. L., Donny, H., Yoshihisa, T., & Naoyuki, T. (2019). Nuclear Transmutation of Long-Lived Fission Product I-129 in Radial Blanket of Sodium-Cooled Fast Reactor. Nuclear Science and Technology, 9(3), 1-8. https://doi.org/10.53747/jnst.v9i3.38

Nuclear Transmutation of Long-Lived Fission Product I-129 in Radial Blanket of Sodium-Cooled Fast Reactor

Peng Hong Liem1,2, Donny Hartanto3, Yoshihisa Tahara1, Naoyuki Takaki1
1 Nippon Advanced Information Service (NAIS Co., Inc.). 416 Muramatsu, Tokai-mura, Naka-gun Ibaraki, Japan
2 Tokyo City University (TCU), 1-28-1 Tamazutsumi, Setagaya, Tokyo, Japan
3 University of Sharjah, P.O. BOX 27272, Sharjah, United Arab Emirates

Main Article Content

Abstract

An investigation on the nuclear transmutation of elemental long-lived fission product (LLFP) in a fast reactor is being conducted focusing on the I-129 LLFP (half-life 15.7 million years) to reduce the environmental burden. The LLFP assembly is loaded into the radial blanket region of a Japanese MONJU class sodium-cooled fast reactor (710 MWth, 148 days/cycle). The iodine element containing I-129 LLFP (without isotope separation) is mixed with YD2 and/or YH2 moderator material to enhance the nuclear transmutation rate. We studied the optimal moderator volume fraction to maximize the transmutation rate (TR, %/year) and the support factor (SF is defined as the ratio of transmuted to produced LLFP). We also investigated the effect of LLFP assembly loading position in the radial blanket and the severe power peak appeared at the fuel assembly adjacent to the LLFP assembly.

Article Details

Keywords

Nuclear transmutation, long-lived fission product, I-129, radial blanket, sodium-cooled fast reactor

References

[1]. Chiba S. et al., “Method to Reduce Long-lived Fission Products by Nuclear Transmutations with Fast Spectrum Reactors,” Sci. Rep., 7, 13961, 2017.
[2]. International Atomic Energy Agency, Evaluation of Actinide Partitioning and Transmutation, Technical Reports Series No. 214, IAEA, Vienna, 1982.
[3]. Osaka M. et al., “Research and Development of Minor Actinide-Containing Fuel and Target in a Future Integrated Closed Cycle System,” Journal of Nuclear Science and Technology, 44(3), 309, 2007.
[4]. Leppänen J. et al. 2015. “The Serpent Monte Carlo Code: Status, Development and Applications in 2013,” Annals of Nuclear Energy, 82, 142, 2015.
[5]. Shibata K. et al., “JENDL-4.0: A New Library for Nuclear Science and Engineering,” Journal of Nuclear Science and Technology, 48, 1, 2011.