Monte Carlo Investigation of the UK’s First EPR Nuclear Reactor Startup Core Using Serpent

Computationally modelling a nuclear reactor startup core for a benchmark against the existing models is highly desirable for an independent assessment informing nuclear engineers and energy policymakers. For the first time, this work presents a startup core model of the UK’s first Evolutionary Press...

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Bibliographic Details
Main Author: Jinfeng Li
Format: Article
Language:English
Published: MDPI AG 2020-10-01
Series:Energies
Subjects:
Online Access:https://www.mdpi.com/1996-1073/13/19/5168
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spelling doaj-f972ce0b2cdd44509ec6e249c6715e0f2020-11-25T03:28:37ZengMDPI AGEnergies1996-10732020-10-01135168516810.3390/en13195168Monte Carlo Investigation of the UK’s First EPR Nuclear Reactor Startup Core Using SerpentJinfeng Li0Department of Electrical and Electronic Engineering, Imperial College London, London SW7 2AZ, UKComputationally modelling a nuclear reactor startup core for a benchmark against the existing models is highly desirable for an independent assessment informing nuclear engineers and energy policymakers. For the first time, this work presents a startup core model of the UK’s first Evolutionary Pressurised Water Reactor (EPR) based on Monte Carlo simulations of particle collisions using Serpent 2, a state-of-the-art continuous-energy Monte Carlo reactor physics burnup code. Coupling between neutronics and thermal-hydraulic conditions with the fuel depletion is incorporated into the multi-dimensional branches, obtaining the thermal flux and fission reaction rate (power) distributions radially and axially from the three dimensional (3D) single assembly level to a 3D full core. Shannon entropy is quantified to characterise the convergence behaviour of the fission source distribution, with 3 billion neutron histories tracked by parallel computing. Source biasing is applied for the variance reduction. Benchmarking the proposed Monte Carlo 3D full-core model against the traditional deterministic transport computation suite used by the UK Office for Nuclear Regulation (ONR), a reasonably good agreement within statistics is demonstrated for the safety-related reactivity coefficients, which creates trust in the EPR safety report and informs the decision-making by energy regulatory bodies and global partners.https://www.mdpi.com/1996-1073/13/19/5168computational neutronicsEuropean pressurised reactorMonte Carlo simulationnuclear physicsnuclear reactor core modellingnuclear energy
collection DOAJ
language English
format Article
sources DOAJ
author Jinfeng Li
spellingShingle Jinfeng Li
Monte Carlo Investigation of the UK’s First EPR Nuclear Reactor Startup Core Using Serpent
Energies
computational neutronics
European pressurised reactor
Monte Carlo simulation
nuclear physics
nuclear reactor core modelling
nuclear energy
author_facet Jinfeng Li
author_sort Jinfeng Li
title Monte Carlo Investigation of the UK’s First EPR Nuclear Reactor Startup Core Using Serpent
title_short Monte Carlo Investigation of the UK’s First EPR Nuclear Reactor Startup Core Using Serpent
title_full Monte Carlo Investigation of the UK’s First EPR Nuclear Reactor Startup Core Using Serpent
title_fullStr Monte Carlo Investigation of the UK’s First EPR Nuclear Reactor Startup Core Using Serpent
title_full_unstemmed Monte Carlo Investigation of the UK’s First EPR Nuclear Reactor Startup Core Using Serpent
title_sort monte carlo investigation of the uk’s first epr nuclear reactor startup core using serpent
publisher MDPI AG
series Energies
issn 1996-1073
publishDate 2020-10-01
description Computationally modelling a nuclear reactor startup core for a benchmark against the existing models is highly desirable for an independent assessment informing nuclear engineers and energy policymakers. For the first time, this work presents a startup core model of the UK’s first Evolutionary Pressurised Water Reactor (EPR) based on Monte Carlo simulations of particle collisions using Serpent 2, a state-of-the-art continuous-energy Monte Carlo reactor physics burnup code. Coupling between neutronics and thermal-hydraulic conditions with the fuel depletion is incorporated into the multi-dimensional branches, obtaining the thermal flux and fission reaction rate (power) distributions radially and axially from the three dimensional (3D) single assembly level to a 3D full core. Shannon entropy is quantified to characterise the convergence behaviour of the fission source distribution, with 3 billion neutron histories tracked by parallel computing. Source biasing is applied for the variance reduction. Benchmarking the proposed Monte Carlo 3D full-core model against the traditional deterministic transport computation suite used by the UK Office for Nuclear Regulation (ONR), a reasonably good agreement within statistics is demonstrated for the safety-related reactivity coefficients, which creates trust in the EPR safety report and informs the decision-making by energy regulatory bodies and global partners.
topic computational neutronics
European pressurised reactor
Monte Carlo simulation
nuclear physics
nuclear reactor core modelling
nuclear energy
url https://www.mdpi.com/1996-1073/13/19/5168
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