IMPROVEMENT TO NEM SP3 MODELLING AND SIMULATION

Yuchao Xu; Jason Hou; Kostadin N. Ivanov

doi:10.1051/epjconf/202124703008

All issues

Volume 247 (2021)

EPJ Web Conf., 247 (2021) 03008

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		03008
Number of page(s)		8
Section		Deterministic Transport
DOI		https://doi.org/10.1051/epjconf/202124703008
Published online		22 February 2021

J. Jiménez, M. Avramova, D. Cuervo, and K. Ivanov. “Comparative analysis of neutronics/thermal-hydraulics multi-scale coupling for LWR analysis.” PHYSOR08 (2008). [Google Scholar]
K. T. Clarno, R. Pawlowski, T. M. Evans, B. Kochunas, and J. Turner. “High fidelity modeling of pellet-clad interaction using the CASL virtual environment for reactor applications.” In Proceedings of the ANS Joint International Conference on Mathematics and Computation (M&C 2015), Supercomputing in Nuclear Applications (SNA) and the Monte Carlo (MC) Method (2015). [Google Scholar]
M. Daeubler, A. Ivanov, B. L. Sjenitzer, V. Sanchez, R. Stieglitz, and R. Macian-Juan. “High-fidelity coupled Monte Carlo neutron transport and thermal-hydraulic simulations using Serpent 2/SUBCHANFLOW.” ANENDJ (2015). [Google Scholar]
M. Daeubler, J. Jimenez, and V. Sanches. “Development of a high-fidelity Monte Carlo thermal-hydraulics coupled code system Serpent/SUBCHANFLOW–first results.” In Proceedings of Physor (2014). [Google Scholar]
R. G. McClarren. “Theoretical aspects of the simplified Pn equations.” TTSPB, (2-4) (2010). [Google Scholar]
S. Thompson and K. Ivanov. “Advances in the Pennsylvania State University NEM code.” ANENDJ (2016). [Google Scholar]
E. Lewis, M. Smith, N. Tsoulfanidis, G. Palmiotti, T. Taiwo, and R. Blomquist. “Benchmark specification for Deterministic 2-D/3-D MOX fuel assembly transport calculations without spatial homogenization (C5G7 MOX).” NEA/NSC (2001). [Google Scholar]
J. Leppänen, M. Pusa, T. Viitanen, V. Valtavirta, and T. Kaltiaisenaho. “The Serpent Monte Carlo code: Status, development and applications in 2013.” In SNA+ MC 2013-Joint International Conference on Supercomputing in Nuclear Applications+ Monte Carlo. EDP Sciences (2014). [Google Scholar]
A. Hébert. “DRAGON5: Designing computational schemes dedicated to fission nuclear reactors for space.” Proceedings of Nuclear and Emerging Technologies for Space (2013). [Google Scholar]
Y. Xu, J. Hou, and K. N. Ivanov. “Implementation of Second-Order Discontinuity Factor for Simplified P3 Theory in NEM.” PHYSOR18 (2018). [Google Scholar]
W. Boyd, S. Shaner, L. Li, B. Forget, and K. Smith. “The OpenMOC Method of Characteristics Neutral Particle Transport Code.” ANENDJ (2014). [Google Scholar]
Y.-A. Chao. “A new and rigorous SPN theory–Part III: A succinct summary of the GSPN theory, the P3 equivalent GSP3 (3) and implementation issues.” ANENDJ (2018). [Google Scholar]

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[1] J. Jiménez, M. Avramova, D. Cuervo, and K. Ivanov. “Comparative analysis of neutronics/thermal-hydraulics multi-scale coupling for LWR analysis.” PHYSOR08 (2008). [Google Scholar]

[2] K. T. Clarno, R. Pawlowski, T. M. Evans, B. Kochunas, and J. Turner. “High fidelity modeling of pellet-clad interaction using the CASL virtual environment for reactor applications.” In Proceedings of the ANS Joint International Conference on Mathematics and Computation (M&C 2015), Supercomputing in Nuclear Applications (SNA) and the Monte Carlo (MC) Method (2015). [Google Scholar]

[3] M. Daeubler, A. Ivanov, B. L. Sjenitzer, V. Sanchez, R. Stieglitz, and R. Macian-Juan. “High-fidelity coupled Monte Carlo neutron transport and thermal-hydraulic simulations using Serpent 2/SUBCHANFLOW.” ANENDJ (2015). [Google Scholar]

[4] M. Daeubler, J. Jimenez, and V. Sanches. “Development of a high-fidelity Monte Carlo thermal-hydraulics coupled code system Serpent/SUBCHANFLOW–first results.” In Proceedings of Physor (2014). [Google Scholar]

[5] R. G. McClarren. “Theoretical aspects of the simplified Pn equations.” TTSPB, (2-4) (2010). [Google Scholar]

[6] S. Thompson and K. Ivanov. “Advances in the Pennsylvania State University NEM code.” ANENDJ (2016). [Google Scholar]

[7] E. Lewis, M. Smith, N. Tsoulfanidis, G. Palmiotti, T. Taiwo, and R. Blomquist. “Benchmark specification for Deterministic 2-D/3-D MOX fuel assembly transport calculations without spatial homogenization (C5G7 MOX).” NEA/NSC (2001). [Google Scholar]

[8] J. Leppänen, M. Pusa, T. Viitanen, V. Valtavirta, and T. Kaltiaisenaho. “The Serpent Monte Carlo code: Status, development and applications in 2013.” In SNA+ MC 2013-Joint International Conference on Supercomputing in Nuclear Applications+ Monte Carlo. EDP Sciences (2014). [Google Scholar]

[9] A. Hébert. “DRAGON5: Designing computational schemes dedicated to fission nuclear reactors for space.” Proceedings of Nuclear and Emerging Technologies for Space (2013). [Google Scholar]

[10] Y. Xu, J. Hou, and K. N. Ivanov. “Implementation of Second-Order Discontinuity Factor for Simplified P3 Theory in NEM.” PHYSOR18 (2018). [Google Scholar]

[11] W. Boyd, S. Shaner, L. Li, B. Forget, and K. Smith. “The OpenMOC Method of Characteristics Neutral Particle Transport Code.” ANENDJ (2014). [Google Scholar]

[12] Y.-A. Chao. “A new and rigorous SPN theory–Part III: A succinct summary of the GSPN theory, the P3 equivalent GSP3 (3) and implementation issues.” ANENDJ (2018). [Google Scholar]