Context-based polynomial extrapolation and slackened synchronization for fast multi-core simulation using FMI

Simulation 2017; 93(3): 185-200 Abir Ben Khaled-El Feki, Laurent Duval, Cyril Faure, Daniel Simon and Mongi Ben Gaid CHOPtrey: Contextual online polynomial extrapolation for enhanced multi-core co-simulation of complex systems Doi: 10.1177/0037549716684026

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On a Roadmap for Future Industrial Nuclear Reactor Core Simulation in the U.K. to Support the Nuclear Renaissance

Energies ◽

10.3390/en11123509 ◽

2018 ◽

Vol 11 (12) ◽

pp. 3509 ◽

Cited By ~ 3

Author(s):

Bruno Merk ◽

Mark Bankhead ◽

Dzianis Litskevich ◽

Robert Gregg ◽

Aiden Peakman ◽

...

Keyword(s):

Nuclear Reactor ◽

Reactor Core ◽

Basic Research ◽

Modelling And Simulation ◽

Software Environment ◽

Specific Detail ◽

Technical Requirements ◽

Strategic Approach ◽

Nuclear Reactor Core ◽

Core Simulation

The U.K. has initiated the nuclear renaissance by contracting for the first two new plants and announcing further new build projects. The U.K. government has recently started to support this development with the announcement of a national programme of nuclear innovation. The aim of this programme with respect to modelling and simulation is foreseen to fulfil the demand in education and the build-up of a reasonably qualified workforce, as well as the development and application of a new state-of-the-art software environment for improved economics and safety. This document supports the ambition to define a new approach to the structured development of nuclear reactor core simulation that is based on oversight instead of looking at detail problems and the development of single tools for these specific detail problems. It is based on studying the industrial demand to bridge the gap in technical innovation that can be derived from basic research in order to create a tailored industry solution to set the new standard for reactor core modelling and simulation for the U.K. However, finally, a technical requirements specification has to be developed alongside the strategic approach to give code developers a functional specification that they can use to develop the tools for the future. Key points for a culture change to the application of modern technologies are identified in the use of DevOps in a double-strata approach to academic and industrial code development. The document provides a novel, strategic approach to achieve the most promising final product for industry, and to identify the most important points for improvement.

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Transient climate simulations of the deglaciation 21–9 thousand years before present; PMIP4 Core experiment design and boundary conditions

Geoscientific Model Development Discussions ◽

10.5194/gmdd-8-9045-2015 ◽

2015 ◽

Vol 8 (10) ◽

pp. 9045-9102 ◽

Cited By ~ 2

Author(s):

R. F. Ivanovic ◽

L. J. Gregoire ◽

M. Kageyama ◽

D. M. Roche ◽

P. J. Valdes ◽

...

Keyword(s):

Working Group ◽

Ad Hoc ◽

Climate Models ◽

Ice Sheet ◽

Before Present ◽

Last Deglaciation ◽

Transient Simulations ◽

The Last Deglaciation ◽

Set Up ◽

Core Simulation

Abstract. The last deglaciation, which marked the transition between the last glacial and present interglacial periods, was punctuated by a series of rapid (centennial and decadal) climate changes. Numerical climate models are useful for investigating mechanisms that underpin the events, especially now that some of the complex models can be run for multiple millennia. We have set up a Paleoclimate Modelling Intercomparison Project (PMIP) working group to coordinate efforts to run transient simulations of the last deglaciation, and to facilitate the dissemination of expertise between modellers and those engaged with reconstructing the climate of the last 21 thousand years. Here, we present the design of a coordinated Core simulation over the period 21–9 thousand years before present (ka) with time varying orbital forcing, greenhouse gases, ice sheets, and other geographical changes. A choice of two ice sheet reconstructions is given, but no ice sheet or iceberg meltwater should be prescribed in the Core simulation. Additional focussed simulations will also be coordinated on an ad-hoc basis by the working group, for example to investigate the effect of ice sheet and iceberg meltwater, and the uncertainty in other forcings. Some of these focussed simulations will focus on shorter durations around specific events to allow the more computationally expensive models to take part.

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Analysis of Modeling Uncertainty Impacts on Nuclear Data Uncertainty Propagation in Core Simulation

10.13182/t123-33308 ◽

2020 ◽

Author(s):

H. Abdel-Khalik ◽

D. Huang

Keyword(s):

Uncertainty Propagation ◽

Nuclear Data ◽

Data Uncertainty ◽

Modeling Uncertainty ◽

Core Simulation

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Molten salt reactor core simulation with PROTEUS

Annals of Nuclear Energy ◽

10.1016/j.anucene.2019.107099 ◽

2020 ◽

Vol 140 ◽

pp. 107099

Author(s):

T. Fei ◽

B. Feng ◽

F. Heidet

Keyword(s):

Molten Salt ◽

Reactor Core ◽

Molten Salt Reactor ◽

Core Simulation

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On the monotonicity preservation of polynomial extrapolation sequences

Applicable Analysis ◽

10.1080/00036817108839019 ◽

1971 ◽

Vol 1 (3) ◽

pp. 283-295

Author(s):

Gerhard Opfer

Keyword(s):

Polynomial Extrapolation

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Towards Development of Uncertainty Library for Nuclear Reactor Core Simulation

Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory ◽

10.1115/icone26-82385 ◽

2018 ◽

Author(s):

Hany S. Abdel-Khalik ◽

Dongli Huang ◽

Ondrej Chvala ◽

G. Ivan Maldonado

Keyword(s):

Cross Sections ◽

Degrees Of Freedom ◽

Nuclear Reactor ◽

Reactor Core ◽

Sensitivity Study ◽

Reactor Physics ◽

Rigorous Approach ◽

Uncertainty Space ◽

Core Simulation

Uncertainty quantification is an indispensable analysis for nuclear reactor simulation as it provides a rigorous approach by which the credibility of the predictions can be assessed. Focusing on propagation of multi-group cross-sections, the major challenge lies in the enormous size of the uncertainty space. Earlier work has explored the use of the physics-guided coverage mapping (PCM) methodology to assess the quality of the assumptions typically employed to reduce the size of the uncertainty space. A reduced order modeling (ROM) approach has been further developed to identify the active degrees of freedom (DOFs) of the uncertainty space, comprising all the cross-section few-group parameters required in core-wide simulation. In the current work, a sensitivity study, based on the PCM and ROM results, is applied to identify a suitable compressed representation of the uncertainty space to render feasible the quantification and prioritization of the various sources of uncertainties. While the proposed developments are general to any reactor physics computational sequence, the proposed approach is customized to the TRITON-NESTLE computational sequence, simulating the BWR lattice model and the core model, which will serve as a demonstrative tool for the implementation of the algorithms.

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