Institute for Neutron Physics and Reactor Technology (INR)

Neutronic / Thermal Hydraulic Coupled codes Based on SP3-Transport Solvers

The second approach is to replace the nodal diffusion codes by transport solvers e.g. SP3, which are able to predict the pin power taking into account local thermal hydraulic feedbacks at pin /subchannel level due to the coupling with a subchannel code. The coupled codes can perform simulations at nodal and pin level.  DYNSUB5.0 is developed at KIT by the internal coupling of DYN3D-SP3 with SubChanFlow. At present, PARCS-SP3 is being coupled with SubChanFlow based on the ICoCo-module for  applications to SMR safety evaluations.

DYNSUB5 is an advanced core simulator for pin and nodal level static and transient simulations of LWR cores. DYNSUB is the internal coupling of DYN3D-SP3 and SubChanFlow developed at KIT. 

Nuclear data (pin / nodal) generated with SERPENT using the in-house utility tools createXSLIB.

PARCS-SP3/SubChanFlow coupling based on ICoCo:  This coupling scheme is under development for the analysis of SMR cores.

Papers

  1. Miriam Knebel, Luigi Mercatali, Victor Sanchez, Robert Stieglitz, Rafael Macian-Juan; Validation of the Serpent 2-DYNSUB code sequence using the Special Power Excursion Reactor Test III (SPERT III). Annals of Nuclear Energy 91 (2016) 79-91
  2. Miriam Daeubler, Nico Trost, Javier Jimenez, Victor Sanchez, Robert Stieglitz, Rafael Macian-Juan; Static and transient pin-by-pin simulations of a full PWR core with the extended coupled code system DYNSUB. Annals of Nuclear Energy 84 (2015) 31–44.  https://doi.org/10.1016/j.anucene.2014.09.057
  3. A. M. Gomez Torres, V. Sánchez, K. Ivanov, R. Macián; DYNSUB: A high fidelity coupled code system for the evaluation of local safety parameters. Part II: Comparison of the different temporal schemes implemented. Annals of Nuclear Energy 48 (2012) 123-129. https://doi.org/10.1016/j.anucene.2012.05.033
  4. A. M. Gomez Torres, V. Sánchez, K. Ivanov, R. Macián Juan; DYNSUB: A high fidelity coupled code system for the evaluation of local safety parameters. Part I: Development, implementation and verification. Annals of Nuclear Energy 48 (2012) 108-122. https://doi.org/10.1016/j.anucene.2012.05.011
  5. A. M. Gomez Torres, V. Sánchez, K. Ivanov, R. Macián; DYNSUB: A high fidelity coupled code system for the evaluation of local safety parameters. Part II: Comparison of the different temporal schemes implemented. Annals of Nuclear Energy 48 (2012) 123-129.
  6.  https://doi.org/10.1016/j.anucene.2012.05.033
  7. A. M. Gomez Torres, V. Sánchez, K. Ivanov, R. Macián Juan; DYNSUB: A high fidelity coupled code system for the evaluation of local safety parameters. Part I: Development, implementation and verification. Annals of Nuclear Energy 48 (2012) 108-122. https://doi.org/10.1016/j.anucene.2012.05.011