OpenMC: A State-of-the-Art Monte Carlo Code for Research and Development

Romano, Paul K.; Horelik, Nicholas; Herman, Bryan; Nelson, Adam G.; Forget, Benoit; Smith, Kord

doi:10.1051/snamc/201406016

Cited by 33 publications

(15 citation statements)

References 11 publications

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“…Continuous integration has been implemented using CircleCI 14 to run a broad range of unit tests and integration tests. The test suite also covers use of the parametrically generated CAD in neutronics simulations using DAGMC 15 and OpenMC 16 . This helps ensure the geometry made is suitable for use in neutronics analysis.…”

Section: Software Practices Employedmentioning

confidence: 99%

The Paramak: automated parametric geometry construction for fusion reactor designs.

et al. 2021

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During the conceptual design process of fusion reactors it is useful to rapidly prototype different design concepts and assess their suitability against a range of high level requirements. Rapid prototyping allows the 'fail early' mantra of other fields to be applied to engineering design. Furthermore, the rapid generation of low fidelity analysis allows fast exploration of design space, which enables better decisions to be made during concept selection and the detailed design phase. The Paramak is an open-source tool that aims to provide automated parameter driven 3D CAD models for fusion reactor components and magnetic fusion reactors. The geometry produced is compatible with several analysis workflows and this allows iterative automated model building and analysis to help steer the design concept optimisation process. The Paramak uses CadQuery 2 to create the 3D CAD model. The Paramak framework is used to create a few example reactor configurations including: a spherical reactor, a regular large radius tokamak and a compact submersion tank reactor. Input parameters for the various reactors that the Paramak can generate generally fall into three categories: continuous ranges such as blanket thickness, integer ranges such as number of toroidal field coils and categorical parameters such as type of divertor. The Paramak facilitates parameter studies where users can investigate the impact of input design parameters on the reactor performance. The use of modern software practices allows the geometry to be continuously tested in analysis workflows to ensure it is fit for purpose. The generation of output metrics from input parameters lends itself to the use of data science and machine learning approaches in order to steer the design. The Paramak provides rapid construction of analysis ready CAD in a manner that allows the designer to save time when exploring the design space for design studies and facilitate automated generative design.

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Section: Software Practices Employedmentioning

confidence: 99%

The Paramak: automated parametric geometry construction for fusion reactor designs.

et al. 2021

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“…To test our numerical implementation, we simulate the volume flux of a free-gas approximated water sphere [14]. The water sphere has a radius of 30 cm, consists of 1 H 16 2 O, and with a density of 1 g/cm 3 . Neutron scattering with both hydrogen and oxygen are simulated by the kernel driven rejection method introduced in section 2.…”

Section: Simulation Of a Water Sphere In The Free-gas Approximationmentioning

confidence: 99%

“…However, between 0.5 eV and the incident energy, i.e., 1 eV, the MCNP6 continuous model overestimates the fluxes by approximately 5%. A later work is performed to use the same continuous cross section with OpenMC [16] to try to identify the source of this overestimation. Such overestimation can not be observed from the spectrum given by OpenMC, indicating that this artefact is originated from the sampling method implemented in MCNP6.…”

Section: Simulation Of a Water Sphere In The Free-gas Approximationmentioning

confidence: 99%

Rejection-based sampling of inelastic neutron scattering

Cai

Kittelmann

Klinkby

et al. 2019

Journal of Computational Physics

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Distributions of inelastically scattered neutrons can be quantum dynamically described by a scattering kernel. We present an accurate and computationally efficient rejection method for sampling a given scattering kernel of any isotropic material. The proposed method produces continuous neutron energy and angular distributions, typically using just a single interpolation per sampling. We benchmark the results of this method against those from accurate analytical models and one of the major neutron transport codes. We also show the results of applying this method to the conventional discrete double differential cross sections.

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“…Here, the deterministic calculation adopts a "two-step" method; namely, the required crosssections of 10 groups with 11 selected boundaries (the data presented in Table 4) are generated by OpenMC 34 and Serpent. Here, the deterministic calculation adopts a "two-step" method; namely, the required crosssections of 10 groups with 11 selected boundaries (the data presented in Table 4) are generated by OpenMC 34 and Serpent.…”

Section: Calculation Toolsmentioning

confidence: 99%

“…The SARAX (System for Advanced Reactor Analysis at Xi'an Jiaotong University, China) code system is a deterministic code system developed for neutronics analysis of reactors and external source-driven subcritical facilities with a fast spectrum. Here, the deterministic calculation adopts a "two-step" method; namely, the required crosssections of 10 groups with 11 selected boundaries (the data presented in Table 4) are generated by OpenMC 34 and Serpent. Furthermore, some of the cross sections at a certain temperature are generated by the NJOY.…”

Section: Calculation Toolsmentioning

confidence: 99%

Neutron physics of the liquid‐fuel heat‐pipe reactor concept with molten salt fuel—Static calculations

et al. 2019

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Summary A liquid‐fuel heat‐pipe reactor (LFHPR) is a novel fast heterogeneous reactor developed by Harbin Engineering University, China, on the basis of liquid‐fuel reactor designs and the heat‐pipe reactor concept. In the concept, the reactor abandons the graphite moderator and keeps neither fuel tubes arranged in the graphite nor fuel rings around the heat pipe. Instead, the reactor applies molten salt fuels, molten metallic eutectic fuels, or other fuels in liquid form. The heat generated in the reactor is removed by the heat pipes driven by liquid metals. With this change, an LFHPR is much more flexible in design and application and able to achieve several advanced features compared with conventional heat‐pipe reactors. In this paper, we describe the general reactor design of an LFHPR, discuss its potential advantages, and give a preliminary verification of the neutron physical feasibility for the reference case, which uses molten salt as the fuel, by using both Monte Carlo and deterministic methods. Results show that the LFHPR yields a hard neutron spectrum that brings a very good neutron economy and is a promising application for breeding. From our approach, we conclude that the proposed LFHPR has a very high power density and high negative temperature feedback coefficient.

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OpenMC: A State-of-the-Art Monte Carlo Code for Research and Development

Cited by 33 publications

References 11 publications

The Paramak: automated parametric geometry construction for fusion reactor designs.

The Paramak: automated parametric geometry construction for fusion reactor designs.

Rejection-based sampling of inelastic neutron scattering

Neutron physics of the liquid‐fuel heat‐pipe reactor concept with molten salt fuel—Static calculations

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