Asymptotic hydrogen redistribution analysis in yttrium-hydride-moderated heat-pipe-cooled microreactors using DireWolf

Terlizzi, Stefano; Labouré, Vincent

doi:10.1016/j.anucene.2023.109735

Cited by 12 publications

(6 citation statements)

References 22 publications

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“…The group structure coincides with that reported in Ref. [2]. The cross sections generated by OpenMC are not directly compatible with the BlueCRAB neutronics solver, Griffin; thus, they were directly converted into ISOXML format by using the Griffin code's newly developed capability to process OpenMC output files.…”

Section: Multigroup Microscopic Cross-section Generationsupporting

confidence: 67%

“…In fact, the original Empire reactor concept is characterized by a moderator temperature coefficient of 5 pcm/K, against a fuel temperature coefficient of -1.2 pcm/K. The design was made generic enough to avoid any proprietary concerns, but specific enough to capture the primary design characteristics of envisioned heat pipe (HP)-cooled monolithic microreactors [2].…”

Section: Model Descriptionmentioning

confidence: 99%

“…To test the workflow, a prototypical microreactor was defined based on the Simplified Microreac-tor Benchmark Assessment (SiMBA) problem presented in Ref. [2]. Feeding time-dependent temperature distributions-computed using BlueCRAB's high-fidelity multi-dimensional models-to MELCOR's release models should enable analysts to improve the accuracy of their results.…”

Section: Introductionmentioning

confidence: 99%

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Development of a BlueCRAB/MELCOR Framework for Supporting Realistic Mechanistic Source Term Calculations in Microreactors

Behne,

Mohammad Jaradat,

Choi

et al. 2023

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Efforts are currently underway to deploy microreactor modeling and simulation tools to better support vendors and regulatory authorities in submitting and reviewing licensing applications. In particular, the Nuclear Regulatory Commission is expected to rely on the Comprehensive Reactor Analysis Bundle (BlueCRAB) multiphysics toolset in performing design-and beyond-design-basis accident analyses. In addition, the Nuclear Regulatory Commission has been using the MELCOR code to estimate mechanistic source terms during accidents. As MELCOR relies on isotopic inventory and reactor temperature/power evolution profiles during accident conditions-all of which can theoretically be obtained from BlueCRAB-the ultimate goal of this activity is to establish a common BlueCRAB-MELCOR framework. However, prior to the present research, BlueCRAB had never been used to calculate such quantities of interest at the full-core level. While there are many Monte Carlo (MC) codes capable of computing such quantities of interest, they are unable to readily account for multiphysics feedback. BlueCRAB allows for the coupling of different physics codes together to perform multiphysics-informed calculations. Therefore, the purpose of this fiscal year 2023 work is to investigate the feasibility and challenges of performing such calculations within BlueCRAB so as to generate the data that MELCOR relies on.To demonstrate the methodology, the proposed workflow was applied to a prototypical heat pipe-cooled microreactor model. To predict isotopic concentrations (taking into account the accumulation of fission products during operation), the necessary microscopic cross sections were generated via OpenMC and tabulated with respect to temperature and burnup. Next, a recently developed capability in Griffin (the reactor physics application in BlueCRAB) was used to convert the OpenMC output format into the ISOXML format used by Griffin. A multiphysics microscopic depletion calculation that involved performing a coupled full-core, heterogeneous neutron transport and thermal calculation at each depletion step was conducted to deplete the core to end of life (EOL) conditions so as to provide both isotopics and the initial condition for the transient calculation. Following a brief null-transient to verify that the initial condition had been properly restarted and was indeed in thermal equilibrium, a heat pipe failure transient was simulated.Thus, the entire workflow of using BlueCRAB to generate MELCOR inputs, from cross-section generation to producing isotopic inventory and power/temperature evolution profiles during transients, is demonstrated. This report also details the identified gaps in the workflow and how they were (for the most part) addressed. Future work should focus on directly including MEL-COR into the workflow by performing a MELCOR calculation using the BlueCRAB-generated input data. In addition, the heat pipe reactor design should be improved so as to reflect more prototypical burnup characteristics at EOL.

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Section: Multigroup Microscopic Cross-section Generationsupporting

confidence: 67%

Section: Model Descriptionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

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Development of a BlueCRAB/MELCOR Framework for Supporting Realistic Mechanistic Source Term Calculations in Microreactors

Behne,

Mohammad Jaradat,

Choi

et al. 2023

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“…The rH-PMR was originally created for a work sponsored by the DOE Microreactor program to perform mechanistic source term calculations through the combined use of the Comprehensive Reactor Analysis Bundle (CRAB) and MELCOR [2]. This work has leveraged and adapted the design described in Reference [3]. Leveraging the previous work allows the team to focus on developing the core of the rHPMR to examine APA, rather than duplicating work.…”

Section: The Realistic Heat-pipe-cooled Microreactormentioning

confidence: 99%

High-Fidelity Neutronics Model of a Realistic Heat Pipe Microreactor Report

Terlizzi,

Trivedi,

Stewart

2024

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This report details the development of a high-fidelity reactor physics model of a generic heatpipe-cooled microreactor (HPMR) -in the neutronics code Serpent-, named the realistic heatpipe-cooled microreactor (rHPMR). The model covers the neutronic characteristics including cycle length, reactivity feedback, and neutron spectrum. The rHPMR provides a generic model that researchers can utilize to make safeguards considerations without disclosing proprietary information. In addition to this, we describe a Python wrapper which automates the generation of Serpent inputs of the rHPMR for the purpose of simulating misuse and diversion scenarios. This wrapper is used to model and simulate a case of fuel misuse and diversion. The rHPMR benchmark is used to exercise the computational tools which will be utilized later for the analysis of the Nuclear Test Reactor (NTR).Negotiations are currently underway between Westinghouse and INL to obtain design information for the NTR. Once the negotiations have been completed, a separate report will be delivered to detail the neutronics characteristics of the NTR.

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“…Additionally, a second heat pipe microreactor model with hydride migration was also included and selected results can be seen in Figure 18. [12] The model is similar to the one above, but captures the feedback that resulted from hydrogen migrating due to temperature and power effects. INL/RPT-23-73834 17…”

Section: Heat Pipementioning

confidence: 99%

Overview of Virtual Test Bed FY23 Activities

Abou Jaoude,

Giudicelli,

Walker

et al. 2023

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This milestone report highlights progress achieved within the Virtual Test Bed (VTB) project during Fiscal Year (FY) 2023. The VTB consists of an open-source repository of state-of-the-art simulation examples for advanced reactor types. Its objective is to help accelerate reactor maturation and deployment by providing 'reference' models that can be openly accessed, improved upon, and re-purposed for proprietary applications. The main accomplishments are summarized below:1. Models on the repository were consistently maintained and new improvements were developed to improve the useability of the website. These new improvements include a tagging system and testing of computationally expensive models.

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Asymptotic hydrogen redistribution analysis in yttrium-hydride-moderated heat-pipe-cooled microreactors using DireWolf

Cited by 12 publications

References 22 publications

Development of a BlueCRAB/MELCOR Framework for Supporting Realistic Mechanistic Source Term Calculations in Microreactors

Development of a BlueCRAB/MELCOR Framework for Supporting Realistic Mechanistic Source Term Calculations in Microreactors

High-Fidelity Neutronics Model of a Realistic Heat Pipe Microreactor Report

Overview of Virtual Test Bed FY23 Activities

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