DEVELOPMENT OF THE MPACT 69-GROUP LIBRARY FOR MAGNOX REACTOR ANALYSIS USING CASL VERA

Kang Seog Kim; Brian J. Ade; Nicholas P. Luciano

doi:10.1051/epjconf/202124710016

All issues

Volume 247 (2021)

EPJ Web Conf., 247 (2021) 10016

References

Open Access

Issue		EPJ Web Conf. Volume 247, 2021 PHYSOR2020 – International Conference on Physics of Reactors: Transition to a Scalable Nuclear Future


Article Number		10016
Number of page(s)		8
Section		Verification & Validation
DOI		https://doi.org/10.1051/epjconf/202124710016
Published online		22 February 2021

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J. Y. Cho, H. G. Joo, K. S. Kim, S. Q. Zee, “Cell Based CMFD Formulation for Acceleration of Whole-core Method of Characteristics Calculation,” J. Korean Nucl. Soc., 34(3), pp. 250–258 (2002). [Google Scholar]
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M. L. Williams, K. S. Kim, “The Embedded Self-Shielding Method,” PHYSOR 2012 – Advances in Reactor Physics – Linking Research, Industry, and Education, Knoxville, TN, USA, April 15–20, 2012 (2012). [Google Scholar]
K. S. Kim, M. L. Williams, D. Wiarda, K. T. Clarno, “Development of the Multigroup Cross Section Library for the CASL Neutronics Simulator MPACT: Method and Procedure,” Ann. Nucl. Energ., 133, pp. 46–58 (2019). [Google Scholar]
K. S. Kim, M. L. Williams, A. Holcomb, D. Wiarda, B. K. Jeon, W. S. Yang, “The SCALE/AMPX Multigroup Cross Section Processing for Fast Reactor Analysis,” Ann. Nucl. Energ., 132, pp. 161–171 (2019). [Google Scholar]
B. R. Herman, B. Forget, K. Smith, “Improved Diffusion Coefficients Generated from Monte Carlo Codes,” 2013 Int. Conf. on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, Sun Valley, ID, USA, May 5–9, 2013 (2013). [Google Scholar]
S. E. Jensen, E. Nonbol, “Description of the Magnox Type of Gas Cooled Reactor (MAGNOX),” NKS-2 ISBN 87-7893-050-2, Riso National Laboratory, Roskilde, Denmark (1999). [Google Scholar]
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K. S. Kim et al., “Development of a Physics Analysis Procedure for the Prismatic Very High Temperature Gas Cooled Reactors,” Ann. Nucl. Energ., 34(11), pp. 849–860 (2007). [Google Scholar]

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[1] MPACT: User’s Manual, Version 1.0.0, November 8, 2013. [Google Scholar]

[2] “Consortium for Advanced Simulation of Light Water Reactors,” http://www.casl.gov/ (2015). [Google Scholar]

[3] J. Turner et al., “The Virtual Environment for Reactor Applications (VERA): Design and architecture,” J. Comput. Phys., 326(1), pp. 544–568 (2016). [Google Scholar]

[4] J. Y. Cho, H. G. Joo, K. S. Kim, S. Q. Zee, “Cell Based CMFD Formulation for Acceleration of Whole-core Method of Characteristics Calculation,” J. Korean Nucl. Soc., 34(3), pp. 250–258 (2002). [Google Scholar]

[5] “SCALE: A Modular Code System for Performing Standardized Computer Analyses for Licensing Evaluation,” ORNL-TM/2005/39, Version 6.2, Oak Ridge National Laboratory, Oak Ridge, TN, USA (2016). (Available from the Radiation Safety Information Computational Center at Oak Ridge National Laboratory as CCC-834.) [Google Scholar]

[6] A. Khairallah, J. Recolin, “Calcul de l’autoprotection résonnante dans les cellules complexes par la méthode des sous-groupes,” Proc. Seminar IAEA-SM-154 on Numerical Reactor Calculations, pp. 305–317, IAEA, Vienna (1972). [Google Scholar]

[7] M. L. Williams, K. S. Kim, “The Embedded Self-Shielding Method,” PHYSOR 2012 – Advances in Reactor Physics – Linking Research, Industry, and Education, Knoxville, TN, USA, April 15–20, 2012 (2012). [Google Scholar]

[8] K. S. Kim, M. L. Williams, D. Wiarda, K. T. Clarno, “Development of the Multigroup Cross Section Library for the CASL Neutronics Simulator MPACT: Method and Procedure,” Ann. Nucl. Energ., 133, pp. 46–58 (2019). [Google Scholar]

[9] K. S. Kim, M. L. Williams, A. Holcomb, D. Wiarda, B. K. Jeon, W. S. Yang, “The SCALE/AMPX Multigroup Cross Section Processing for Fast Reactor Analysis,” Ann. Nucl. Energ., 132, pp. 161–171 (2019). [Google Scholar]

[10] B. R. Herman, B. Forget, K. Smith, “Improved Diffusion Coefficients Generated from Monte Carlo Codes,” 2013 Int. Conf. on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, Sun Valley, ID, USA, May 5–9, 2013 (2013). [Google Scholar]

[11] S. E. Jensen, E. Nonbol, “Description of the Magnox Type of Gas Cooled Reactor (MAGNOX),” NKS-2 ISBN 87-7893-050-2, Riso National Laboratory, Roskilde, Denmark (1999). [Google Scholar]

[12] N. P. Luciano, B. J. Ade, K. S. Kim, “Verification of MPACT using Magnox Reactor Neutronics Progression Problems,” (forthcoming) PHYSOR 2020, Cambridge, United Kingdom, March 29–April 2, 2020 (2020). [Google Scholar]

[13] K. S. Kim et al., “Development of a Physics Analysis Procedure for the Prismatic Very High Temperature Gas Cooled Reactors,” Ann. Nucl. Energ., 34(11), pp. 849–860 (2007). [Google Scholar]