Recent updates on perturbation analysis of the KALIMER-600 TRU burner
Main Article Content
Abstract
Sodium void worth and the Doppler coefficient, which are very important safety parameters in safety analysis of the KALIMER-600 TRU burner, should be carefully evaluated. A perturbation analysis for the TRU burner has thus been performed using the perturbation method, not only to make sure the reactivity feedbacks meet the predetermined design targets but also to obtain insight into the actual physical processes in response to severe coolant voiding accidents. The more detailed
information on the actual physical phenomena that can be achieved, the more helpful it can be to the safety design and analysis of the TRU burner. Hence, a perturbation code, PERT-K, has been developed by the Korea Atomic Energy Research Institute based on the diffusion code, DIF3D,to allow reactivity effect breakdown calculations for fast reactor analysis. This paper presents recent updates on a perturbation analysis of the KALIMER-600 TRU burner using DIF3D and PERT-K. The currently developed isotope-wise reactivity module of PERT-K is described along with an analysis of the scenarios of whole core voiding and fuel temperature change in the TRU burner. The perturbation results are believed to be useful for further optimization of the passive safety characteristics of the
TRU burner.
Article Details
Keywords
TRU burner, sodium void worth, Doppler effect, perturbation method, PERT-K, DIF3D, isotope-wise reactivity
References
[2] Hahn, D. et al., “KALIMER-600 Conceptual Design Report”, KAERI/TR-3381/2007, KAERI, 2007.
[3] D. H. Hahnet al., “Advanced SFR Design Concepts and R&D Activities”, Nuclear Engineering and Technology, Vol.41, No.4, p. 427-446, 2009.
[4] Y. I. Kim et al., “Preliminary Conceptual Design Report of Gen-IV SFR Demonstration Plant”, KAERI/TR-4335/2011, KAERI, 2011 (in Korean).
[5] K. L. Derstine, “DIF3D: A Code to Solve One-, Two-, and Three-Dimensional FiniteDifference Diffusion Theory Problems”, ANL-82-64, ANL,1984.
[6] T. K. Kim et al., “Development of a Perturbation Code, PERT-K, for Hexagonal Core Geometry”, KAERI/TR-1194/98, KAERI, 1998.
[7] J. W. Jang et al., “Development of a Perturbation Theory Module for Triangular-Z Geometry”, Transactions of the Korean Nuclear Society Spring Meeting, Jeju, Korea, May 10-11, 2007.
[8] P. N. V. Ha et al., “Improvement, Verification and Validation of PERT-K 0.0”, SFR-DR141- TE-02-2012.Rev.00, KAERI, 2012.
[9] P. N. V. Ha et al., “Development of an Isotope-wise Reactivity Module for the Triangular-Z Geometry in PERT-K 0.0”, SFR-DR141-TE-03-2012.Rev.00, KAERI, 2012.
[10] R. E. Macfarlane, “TRANSX-2: A Code for Interfacing MATXS Cross Section Libraries to Nuclear Transport Codes”, LA-12312-MS, LANL, 1993.
[11] R. E. Alcouffe, “User’s Guide for TWODANT: A Code Package for TwoDimensional, Diffusion-Accelerated, Neutron Transport”, LA-10049-M, LANL, 1990.