Comparative Analysis of Reactivity Calculations for the CERMET Fueled ADS with Serpent and MCNP6 Codes
Main Article Content
Abstract
The ADS (accelerator driven system) is recognized as a promising system to annihilate the radioactivity of nuclear waste with its inherent safety feature and waste transmutation potential. Thus, conceptual designs of ADS are widely carrying out. In order to verify the accuracy of an innovative ADS core modeling by using simulation codes, the reactivity calculations of CERMET fueled ADS were conducted using two Monte Carlo codes, Serpent and MCNP6 with ENDF/B-VII.0 library. The comparison shows a good agreement between two codes including the eigenvalue (less than 50 pcm) and fuel temperature feedback (discrepancy is within the standard deviation). It implies that the ADS was modelled successfully and can be used for further investigation.
Keywords: CERMET fueled ADS, Serpent code, MCNP6, reactivity calculation.
Keywords:
CERMET fueled ADS, Serpent code, MCNP6, reactivity calculation.
References
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[4] Herrera-Martinez, Transmutation of Nuclear Waste in Accelerator-Driven System, PhD thesis, University of Cambridge, 2004.
[5] Thanh Mai Vu and Takanori Kitada, Seed and blanket ADS using thorium – reprocessed fuel: Parametric survey on TRU transmutation performance and safety characteristics, Ann. Nucl. Energy vol. 78, 176-179, April, https://doi.org/10.1016/j.anucene.2014.12.018, 2015.
[6] Thanh Mai Vu and Takanori Kitada, Seed and blanket thorium-reprocessed fuel ADS: multi-cycle approach for higher thorium utilization and TRU transmutation, Ann. Nucl. Energy vol. 75, 438-442, January, https://doi.org/10.1016/j.anucene.2014.08.025, 2015.
[7] D. Haas et al., CERMET fuel behavior and properties in ADS reactors, Energy Conversion and Management vol. 49, issue 7, 1928-1933, https://doi.org/10.1016/j.enconman.2007.12.027, 2008.
[8] Leppanen, J., Pusa, M., Viitanen, T., Valtavirta, V., Kaltiaisenaho, T., 2015. The Serpent Monte Carlo code: status, development and applications in 2013. Ann. Nucl. Energy 82, 142–150, https://doi.org/10.1016/j.anucene.2014.08.024, 2015.
[9] D. B. Pelowitz, MCNP6 User Manual, Version 10, 2013.
[10] M. B. Chadwick, P. Obloˇzinsk´y, M. Herman et al., ENDF/B-VII.0: next generation evaluated nuclear data library for nuclear science and technology, Nucl. Data Sheets, Special Issue on Evaluated Nuclear Data File ENDF/B-VII.0, https://doi.org/10.1016/j.nds.2006.11.001, 2006.
[11] Leppänen, J., Pusa, M., Fridman, E., Overview of methodology for spatial homogenization in the Serpent 2 Monte Carlo code, Ann. Nucl. Energy 96, 126-136, https://doi.org/10.1016/j.anucene.2016.06.007, 2016.
[12] Novak, O., et al., Rod drop transient at VR-1 reactor – Experiment and Serpent transient calculation, Ann. Nucl. Energy 141, 107296, https://doi.org/10.1016/j.anucene.2019.107296, 2020.
[13] Fridman, E., Valtavirta, V., Aufiero, M., Nuclear data sensitivity and uncertainty analysis of critical VENUS-F cores with the Serpent Monte Carlo code, Ann. Nucl. Energy 138, 107196, https://doi.org/10.1016/j.anucene.2019.107196, 2020.
[14] Gulik, V., Tkaczyk, A. H., Cost optimization of ADS design: Comparative study of externally driven heterogeneous and homogeneous two-zone subcritical reactor systems, Nucl. Eng. Des. 270, 133-142, https://doi.org/10.1016/j.nucengdes.2014.01.007, 2014.
[15] Gohar, Y., Chao, Y., Kraus, A. R., Accelerator-Driven Subcritical System for Disposing of the U.S. Spent Nuclear Fuel Inventory, ANL-18/07, Argonne National Laboratory, 2018.