Article Sidebar

Published: 2011-06-30
Abstract Views: 71
DOI: https://doi.org/10.53747/nst.v1i2.303
Issue
Vol. 1 No. 2 (2011)
Section
Articles
How to Cite
PHAM , N. V. H., YOO, J. ., JANG, J. ., & KIM, S.-J. . (2011). APPLICABILITY OF THE PERTURBATION THEORY CODE PERT-K TO PERTURBATION ANALYSIS IN KALIMER-600. Nuclear Science and Technology, 1(2), 52-57. https://doi.org/10.53747/nst.v1i2.303

APPLICABILITY OF THE PERTURBATION THEORY CODE PERT-K TO PERTURBATION ANALYSIS IN KALIMER-600

PHAM NHU VIET HA1, JAEWOON YOO1, JINWOOK JANG1, SANG-JI KIM2
1 Korea Atomic Energy Research Institute 1045 Daedeok-daero, Yuseong-ku, Daejeon, 305-353, Korea
2 Korea Atomic Energy Research Institute 1045 Daedeok-daero, Yuseong-ku, Daejeon, 305-353, Korea *

Main Article Content

Abstract

PERT-K is a diffusion perturbation theory code developed by the Korea Atomic Energy Research Institute (KAERI) for use in fast reactor analysis. In past years, KAERI has also been developing an advanced fast reactor concept, KALIMER-600, which is a pool-type, liquid metal sodium cooled, metallic-fuelled fast reactor. For safety design, the reactivity effects in KALIMER-600 should be properly assessed. In this paper, various reactivity effects of importance in KALIMER-600 due to sodium void and fuel temperature change will be analyzed using PERT-K so as to examine its applicability to such reactivity feedback calculations in relation to the direct flux computations for the unperturbed and perturbed systems. It is found that the calculation results by PERT-K agree well with those by the diffusion code DIF3D.

Article Details

Keywords

liquid metal reactor, reactivity effects, sodium void, fuel temperature change, perturbation theory, PERT-K, DIF3D

References

[1] KIM, T.K. et al. (1998). “Development of a perturbation code for hexagonal core,” Proceedings of ’98 KNS Autumn Meeting, Korean Nuclear Society.
[2] JANG, J.W. et al. (2007). “Development of a perturbation theory module for triangular-z geometry,” Proceedings of ’07 KNS Spring Meeting, Korean Nuclear Society.
[3] DERSTINE, K.L. (1984). “DIF3D: A code to solve one-, two- and three-dimensional finite-difference diffusion theory problems,” ANL-82-64, Argonne National Laboratory.
[4] HAHN, D. et al. (2004). “KALIMER-600 preliminary conceptual design report,” KAERI/TR-2784/2004, KAERI.
[5] LEE, Y.B. et al. (2006). “Safety analysis for key design features of KALIMER-600 design concept,” KAERI/TR-3172/2006, KAERI.
[6] KIM, Y.I. et al. (2011). “Preliminary Conceptual Design Report of Gen-IV SFR Demonstration Plant,” KAERI/TR-4335/2011, KAERI (in Korean).