Application of automatic few-group structure optimization based on perturbation theory to VHTR cores
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초록
A new automatic group structure optimization method based on the perturbation theory was proposed for the few-group structure in two-step nuclear design procedure for VHTR. It applies the sensitivity coefficient of the perturbation theory which includes not only the effect of the cross section on the multiplication factor but also the adjoint weighted reaction rate. The sensitivity coefficient of the fine group for the multiplication factor was calculated and the group boundary for a few-group can be determined so that the summation of the fine group sensitivity for a few-group should be evenly distributed over every few-group. This method was successfully implemented in the ABGO code. VHTR-350 and MiHTR 2D core were used to investigate the performance and applicability of the proposed method. The code generated the new group structures for two cores and the error of the multiplication and reaction rate by the new group structure was compared with the result by the fine group structure. The comparisons indicate that the new group structure by the proposed method can provide the multiplication factor and reaction rates comparable to the existing group structure and more accurate results than the group structure obtained using the Contributon theory.
Abstract
A new automatic group structure optimization method based on the perturbation theory was proposed for the few-group structure in two-step nuclear design procedure for VHTR. It applies the sensitivity coefficient of the perturbation theory which includes not only the effect of the cross section on the multiplication factor but also the adjoint weighted reaction rate. The sensitivity coefficient of the fine group for the multiplication factor was calculated and the group boundary for a few-group can be determined so that the summation of the fine group sensitivity for a few-group should be evenly distributed over every few-group. This method was successfully implemented in the ABGO code. VHTR-350 and MiHTR 2D core were used to investigate the performance and applicability of the proposed method. The code generated the new group structures for two cores and the error of the multiplication and reaction rate by the new group structure was compared with the result by the fine group structure. The comparisons indicate that the new group structure by the proposed method can provide the multiplication factor and reaction rates comparable to the existing group structure and more accurate results than the group structure obtained using the Contributon theory.
참고문헌 (12)
- J. Y. Cho, "Improvement and verification of the DeCART code for HTGR core physics analysis", Nucl. Eng. Technol, 51, pp.13~30 (2019)
- H.C. Lee, "Development of HELIOS", CAPP code system for the analysis of block type VHTR cores, 2012, ~
- R. J. Stammler, "HELIOS Methods", ~ (2004)
- K. S. Kim, "Development of the optimization procedure for the number of neutron energy groups and boundaries in the VHTR physics analysis", Korean Nuclear Society Autumn Meeting (2006)
- V. F. Fallah, "Optimization of neutron energy-group structure in thermal lattices using ultrafine bilinear adjoint function", Prog. Nucl. Energy, 85, pp.648~658 (2015)
- F. A. Alpha, "Advanced Methodology for Selecting Group Structures for Multigroup Cross Section Generation", PHYSOR2000 (2000)
- M. L. Williams, "Generalized Contributon response theory", Nucl. Sci. Eng, 108, pp.355~383 (1991)
- D. G. Cacuci, "Sensitivity and Uncertainty Analysis, vol. 1", pp.2003, Chapman & Hall
- T. Y. Han, "Development of a sensitivity and uncertainty analysis code for high temperature gas-cooled reactor physics based on the generalized perturbation theory", Ann. Nucl. Energy, 85, pp.501~511 (2015)
- Neutronics and Safety Analysis Coupling for VHTR Accidents: DesignBasis Accident and beyond Design-Basis Accident, "S. S. Yuk", KAERI, ~, pp.KAERI (2022), TR-9287[DOI]
- C.K. Jo, "Core Nuclear Design of a Micro Modular High Temperature Gas-Cooled Reactor", Korean Nuclear Society Autumn Meeting
- OECD benchmark for prismatic coupled neutronics, "thermal fluids transient of the MHTGR-350 MW core design: benchmark definition", J. Ortensi, 2013