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Published: 2016-09-30
Abstract Views: 120
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DOI: https://doi.org/10.53747/jnst.v6i3.158
Issue
Vol. 6 No. 3 (2016)
Section
Articles
How to Cite
Hoang , V. K., Hoang Thanh , P. H., & Tran , H. N. (2016). Neutronics feasibility of using Gd₂O₃ particles in VVER-1000 fuel assembly. Nuclear Science and Technology, 6(3), 1-7. https://doi.org/10.53747/jnst.v6i3.158

Neutronics feasibility of using Gd₂O₃ particles in VVER-1000 fuel assembly

Hoang Van Khanh1, Hoang Thanh Phi Hung2, Tran Hoai Nam3
1 Institute for Nuclear Science and Technology, VINATOM, 179 Hoang Quoc Viet, Hanoi, Vietnam
2 Nuclear Training Center, VINATOM, 140 Nguyen Tuan, Hanoi, Vietnam
3 Institute of Research and Development, Duy Tan University, Da Nang, Vietnam

Main Article Content

Abstract

Neutronics feasibility of using Gd2O3 particles for controlling excess reactivity of VVER-1000 fuel assembly has been investigated. The motivation is that the use of Gd2O3 particles would increase the thermal conductivity of the UO2+Gd2O3 fuel pellet which is one of the desirable characteristics for designing future high burnup fuel. The calculation results show that the Gd2O3 particles with the diameter of 60 µm could control the reactivity similarly to that of homogeneous mixture with the same amount of Gd2O3. The power densities at the fuel pin with Gd2O3 particles increase by about 10-11%, leading to the decrease of the power peak and a slightly flatter power distribution. The power peak appears at the periphery pins at the beginning of burnup process which is decreased by 0.9 % when using Gd2O3 particles. Further work and improvement are being planned to optimize the high power peaking at the beginning of burnup.

Article Details

Keywords

Fuel assembly, Gd₂O₃ particle, power distribution, VVER

References

[1] S. Fukushima, T. Ohmichi, A. Maeda, H. Watanabe, "The effect of gadolinium content on the thermal conductivity of near-stoichiometric (U,Gd)O2 solid solutions". J. Nucl. Mater., 105, 201–210, 1982.
[2] M. Amaya, M. Hirai, H. Sakurai, K. Ito, M. Sasaki, T. Nomata, K. Kamimura, R. Iwasaki, "Thermal conductivities of irradiated UO2 and (U,Gd)O2 pellets". J. Nucl. Mater., 300, 57–64, 2002.
[3] D. Balestrieri, IAEA Technical Committee Meeting on Advances in Pellet Technology for Improved Performance at High Burnup, Paper No. 2-1, 1996.
[4] K. Iwasaki, T. Matsui, K. Yanai, R. Yuda, Y. Arita, T. Nagasaki, N. Yokoyama, I. Tokura, K. Une, K. Harada, "Effect of Gd2O3 dispersion on the thermal conductivity of UO2". J. Nucl. Sci. Technol., 46:7, 673-676, 2009.
[5] NEA/NSC/DOC 10, Nuclear Energy Agency, Organization for Economic Co-operation and Development, 2002.
[6] Nagaya, Y., Okumura, K., Mori, T., Nakagawa, M., MVP/GMVP II: general purpose Monte Carlo codes for neutron and photon transport calculations based on continuous energy and multigroup methods. JAER, I–1348, 2005.
[7] Shibata, K., et al., "Japanese evaluated nuclear data library version 3 revision-3: Jendl-3.3", J. Nucl. Sci. Technol. 39, 1125–1136, 2002.
[8] H.N. Tran, Y. Kato, "An optimal loading principle of burnable poisons for an OTTO refueling scheme in pebble bed HTGR cores". Nucl. Eng. Des 239, 2357–2364, 2009.
[9] H.N. Tran, V.K. Hoang, "Neutronic characteristics of an OTTO refueling PBMR". Nucl. Eng. Des. 253, 269– 276, 2012.