Two-step neutronics calculations with Shift and Griffin for advanced reactor systems

Pandya, Tara; Bostelmann, Friederike; Jessee, Matthew Anderson; Ortensi, Javier

doi:10.1016/j.anucene.2022.109131

Cited by 14 publications

(13 citation statements)

References 21 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…This section documents the verification of the automated cross section generation procedure implemented into Shift by comparing results to those of the Empire microreactor benchmark previously published [2].…”

Section: Verification Of Automated Cross Section Generationmentioning

confidence: 99%

“…Previously, the process to generate multigroup cross sections with Shift entailed processing the Shift raw tallies from an Hierarchical Data Format 5 (HDF5) output via a Python script to convert them to cross sections and then to the Griffin ISOXML format (see Section 2 in the associated journal paper [2] for full details). In FY22, Shift was updated to automatically calculate and output the multigroup cross sections directly to HDF5 along with the raw tallies.…”

Section: Verification Of Automated Cross Section Generationmentioning

confidence: 99%

“…To verify this new automated implementation, multigroup cross sections were generated with Shift for the 2D Empire assembly benchmark and compared to the previously generated cross sections from FY21 and published in Pandya [1,2]. The same Shift model and input from FY21 were used with modification needed only to the tally input block.…”

Section: Listing 3 Example Shift Tally Input To Generate Multigroup C...mentioning

confidence: 99%

“…This report presents the performance enhancements, multigroup cross section production automation, and other advanced features added to Shift during FY22. This work builds upon several technical reports and the content of a published journal paper [1,2]. The geometric tracking performance enhancements added to Shift in this work target more efficient computations of TRISO-fueled advanced reactors.…”

mentioning

confidence: 99%

See 3 more Smart Citations

Modeling, Performance Assessment, and Nodal Data Analysis of TRISO-Fueled Systems with Shift

Pandya¹,

Bostelmann²,

Jessee³

et al. 2022

View full text Add to dashboard Cite

Section: Verification Of Automated Cross Section Generationmentioning

confidence: 99%

Section: Verification Of Automated Cross Section Generationmentioning

confidence: 99%

Section: Listing 3 Example Shift Tally Input To Generate Multigroup C...mentioning

confidence: 99%

mentioning

confidence: 99%

See 2 more Smart Citations

Modeling, Performance Assessment, and Nodal Data Analysis of TRISO-Fueled Systems with Shift

Pandya¹,

Bostelmann²,

Jessee³

et al. 2022

View full text Add to dashboard Cite

“…• A Shift model of the HP-MR was developed by ORNL in FY-2022 for diffusion crosssection and SPH factors generation [18]. Similar approach should be applied in multiphysics transients calculations leveraging the newly developed pin-power reconstruction approach within Griffin [19].…”

Section: Future Work Recommendedmentioning

confidence: 99%

Multiphysics Analysis of Load Following and Safety Transients for MicroReactors

Stauff¹,

Abdelhameed²,

Cao³

et al. 2022

View full text Add to dashboard Cite

The tools developed within the U.S. Department of Energy (DOE) Office of Nuclear Energy's Nuclear Energy Advanced Modeling and Simulation (NEAMS) program aim at providing highfidelity multiphysics modeling capabilities to support design and licensing of various types of advanced nuclear reactors, including the technologies being developed by U.S. microreactor vendors relying on heat pipe and gas-cooled technologies. In FY-2022, the NEAMS Multiphysics Applications team made significant progress both in demonstrating capabilities applied to microreactor problems, and in supporting NEAMS developers.Three microreactor models were developed through this project to support a demonstration of NEAMS tools capabilities for solving challenging microreactor modeling problems:1-The Heat Pipe MicroReactor (HP-MR) unit-cell and full core models developed in FY-2021 were updated with increased fidelity. This work demonstrates the capability to perform high-fidelity multiphysics load-following and heat pipe cascading failures using coupled Griffin-BISON-Sockeye simulations. Such analysis confirmed the HP-MR concept ability to operate in a flexible way and for the reactor to follow the load, and its ability to avoid heat pipe cascading failure unless designed with high power close to operating failure limits of its heat pipes.2-A Gas-Cooled MicroReactor (GC-MR) assembly model was developed incorporating various modeling challenges expected for horizontal gas-cooled microreactors. A wide range of high-fidelity multiphysics transient analyses were simulated by coupling Griffin/BISON/SAM. These simulations showcased various types of load-following transients (large daily or short frequent power variations) and accidental transients that are specific to GC-MRs (flow blockage, depressurization, etc.). This initial analysis confirms the ability of the GC-MR to withstand such accidental transients without leading to severe accidents. Leveraging this experience, a full core GC-MR was also modelled based on industry design and initial steady-state multiphysics simulations (Griffin/SAM) were completed.3-An initial model of the Kilopower Reactor Using Stirling Technology (KRUSTY) experiment was developed leveraging initial work performed at LANL. This model was significantly updated and improved, and initial steady-state multiphysics simulations (with coupled Griffin/BISON/Sockeye) were completed.

show abstract

Precisely Predicting Neutronics Parameters of Nuclear Reactor

Zhong,

Feng,

et al. 2024

Lecture Notes in Computer Science

View full text Add to dashboard Cite

Two-step neutronics calculations with Shift and Griffin for advanced reactor systems

Cited by 14 publications

References 21 publications

Modeling, Performance Assessment, and Nodal Data Analysis of TRISO-Fueled Systems with Shift

Modeling, Performance Assessment, and Nodal Data Analysis of TRISO-Fueled Systems with Shift

Multiphysics Analysis of Load Following and Safety Transients for MicroReactors

Precisely Predicting Neutronics Parameters of Nuclear Reactor

Contact Info

Product

Resources

About