FY17 Status Report on NEAMS Neutronics Activities

Lee, C. H.; Jung, Yeon Sang; Smith, M. A.

doi:10.2172/1414286

Cited by 6 publications

(10 citation statements)

References 2 publications

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“…power, to the T/H solver. In order to update cross sections in accordance to temperature and density changes resulted from the feedback calculation, the feedback framework is linked to the CSAPI and ISOPAR [12] routines. Using this framework, PROTEUS-MOC can be coupled to the internal and external T/H solver such as a sub-channel code.…”

Section: T/h Feedback Frameworkmentioning

confidence: 99%

“…(The purple-colored boxes denote the codes developed by the Argonne neutronics team) Last year, an advanced nodal solver was implemented to PROTEUS for use in routine nuclear reactor design and analysis. [12] A simplified thermal-hydraulic (T/H) module was added to the NODAL and MOC solvers of PROTEUS to perform the thermal feedback calculation in a time efficient manner, compared to the coupled simulation with external T/H codes such as Nek5000. Significant performance improvements were made to PROTEUS-MOC using the coarse mesh finite difference (CMFD) numerical acceleration and code optimization.…”

Section: Introductionmentioning

confidence: 99%

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FY18 Progress on Improvements and V&V of MC<sup>2</sup>-3 and PROTEUS

Lee

Jung

2018

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The PROTEUS code is a high-fidelity capable deterministic neutron transport code based on unstructured finite element meshes, which solves the steady-state and transient neutron transport problem using the 2 nd -order discrete ordinate method (SN2ND), the method of characteristics (MOC), and the advanced nodal transport method (NODAL). The PROTEUS system in a broader sense consists of cross section generation tools, mesh generation tools, and output post processing tools as well as neutron transport solvers.The main accomplishments in the FY18 NEAMS neutronics tasks are that the computational performance and the simplified thermal feedback of PROTEUS-MOC were significantly improved, that the transient simulation capability as well as the molten salt reactor (MSR) simulation capabilities were successfully implemented to PROTEUS-NODAL, that the MC 2 -3 versions with the updated thermal cross section capability and threedimensional MOC capability were integrated, and that further verification and validation tests were performed with the updated PROTEUS demonstrating the applicability and accuracy of the code.The computational performance of PROTEUS-MOC was upgraded by implementing the partial-current based coarse mesh finite difference (CMFD) option, the conventional transport sweeping option, and the preconditioner to the steady-state CMFD solution scheme. In addition, the multigroup CMFD option was added to the transient solution scheme, showing significant improvements in the computational performance.

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Section: T/h Feedback Frameworkmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

FY18 Progress on Improvements and V&V of MC<sup>2</sup>-3 and PROTEUS

Lee

Jung

2018

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“…PROTEUS is a code package under development of NEAMS project, which includes three different neutronics solvers: SN (discrete ordinates), MOC (method of characteristics) and NODAL (nodal transport) [3]. PROTEUS-MOC (MOCEX) is used in this study to generate the whole core reference solution.…”

Section: Introductionmentioning

confidence: 99%

Implementation and Comparison of Lattice Module and Discontinuity Factors Module in Proteus Toolsets

Hou

Avramova

2021

EPJ Web Conf.

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State-of-the-art core nodal diffusion calculation involves the use of assembly discontinuity factor (ADF) to improve computational accuracy by introducing degree of freedom describing the relationship between interfacial discontinuities in nodal calculation [1]. The form of ADF known as the Flux based ADF (FDF) generated from flux information is recommended in the conventional two-level core calculation scheme. The multi-group cross-sections were generated using SCALE 6.2 NEWT and verified with KENO-VI [2]. A lattice module has been created for the high-fidelity neutron transport code MOCEX [3] to generate the group constants and side-independent ADFs. This new capability is verified against the reference code SCALE 6.2 NEWT under both serial and parallel modes. The implementation of ADF is performed in this work and further verified by comparing core keff. The calculation results show that the newly implemented ADF module consistently improved the accuracy of the PROTEUS-NODAL (NODAL) diffusion solver, which will become an affordable candidate for the following research of High-to-Low (Hi2Lo) transport-to-diffusion informing scheme [4].

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“…This increases the need for advanced design analysis capabilities for MSR applications. In order to meet this need for MSR modeling and simulation capabilities, it was decided to extend the capabilities of the PROTEUS-NODAL code [4,5] being developed at Argonne National Laboratory for the steady state and transient analyses of MSRs. PROTEUS-NODAL is a three-dimensional (3D) neutron transport code based on a homogeneous assembly model for various nuclear reactor applications.…”

Section: Introductionmentioning

confidence: 99%

Multiphysics Coupling of PROTEUS-NODAL and SAM for Molten Salt Reactor Simulation

Jaradat

Yang

Park

et al. 2020

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Verification tests of the coupled system of PROTEUS-NODAL and SAM were performed using the steady state and transient problems derived from the MSFR benchmark problem. Since the radial crossflow is neglected in the current SAM model, the effect of this simplification was first examined by comparing the steady state results with those obtained by a manually coupled calculation of PROTEUS-NODAL and ANSYS CFX. The SAM calculation used four parallel axial channels and CFX performed the full 3D CFD calculation in the cylindrical geometry of the MSFR core. Due to the neglect of the radial velocity field in the SAM calculation, SAM underestimated the axial velocity at the core center slightly, and this resulted in a slightly top-skewed power distribution: 0.1% overestimation in the upper part and 0.2% underestimation in the lower part of the core. The UTOP, ULOF, and ULOHS accidents of the MSFR transient benchmark were analyzed by including the outer loop in the SAM model. The results were compared with the PSI solutions from a coupled PARCS and TRACE calculation and the TUDelft solutions obtained from a coupled neutron diffusion and CFD calculation. In general, the power and core-averaged fuel temperature solutions of the coupled PROTEUS-NODAL and SAM calculations agreed well with the other solutions.

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FY17 Status Report on NEAMS Neutronics Activities

Cited by 6 publications

References 2 publications

FY18 Progress on Improvements and V&V of MC<sup>2</sup>-3 and PROTEUS

FY18 Progress on Improvements and V&V of MC<sup>2</sup>-3 and PROTEUS

Implementation and Comparison of Lattice Module and Discontinuity Factors Module in Proteus Toolsets

Multiphysics Coupling of PROTEUS-NODAL and SAM for Molten Salt Reactor Simulation

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