Beryllium erosion and redeposition in ITER H, He and D-T discharges

Abstract The Monte-Carlo code ERO2.0 was used to simulate steady-state erosion and transport of beryllium (Be) in the ITER main chamber. Various plasma scenarios were tested, including a variation of the main species (hydrogen, deuterium, helium), plasma conditions (density, temperature, flow velocity) and magnetic configurations. The study provides valuable predictions for the Be transport to the divertor, where it is expected to be an important contributor to dust formation and fuel retention due to build-up of co-deposited layers. The Be gross and net erosion rates provided by this study can help identifying first wall regions with potentially critical armour lifetime.

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Unstructured Mesh–Based Neutronics and Thermomechanics Coupled Steady-State Analysis on Advanced Three-Dimensional Fuel Elements with Monte Carlo Code iMC

Nuclear Science and Engineering ◽

10.1080/00295639.2020.1839342 ◽

2021 ◽

pp. 1-14

Author(s):

HyeonTae Kim ◽

Yonghee Kim

Keyword(s):

Monte Carlo ◽

Steady State ◽

Unstructured Mesh ◽

Three Dimensional ◽

Monte Carlo Code ◽

Steady State Analysis ◽

Fuel Elements ◽

State Analysis

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The Modelling and Coupling Methodology of ANSYS CFX Using Porous Media for PB-AHTR

Volume 3: Nuclear Safety and Security; Codes, Standards, Licensing and Regulatory Issues; Computational Fluid Dynamics and Coupled Codes ◽

10.1115/icone21-16687 ◽

2013 ◽

Author(s):

Linsen Li ◽

Haomin Yuan ◽

Kan Wang

Keyword(s):

Porous Media ◽

Monte Carlo ◽

Steady State ◽

High Temperature ◽

Monte Carlo Code ◽

First Principle ◽

Pebble Bed ◽

Coupled Calculation ◽

Ansys Cfx ◽

High Temperature Reactor

This paper introduces a first-principle steady-state coupling methodology using the Monte Carlo Code RMC and the CFD code CFX which can be used for the analysis of small and medium reactors. The RMC code is used for neutronics calculation while CFX is used for Thermal-Hydraulics (T-H) calculation. A Pebble Bed-Advanced High Temperature Reactor (PB-AHTR) core is modeled using this method. The porous media is used in the CFX model to simulate the pebble bed structure in PB-AHTR. This research concludes that the steady-state coupled calculation using RMC and CFX is feasible and can obtain stable results within a few iterations.

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Coupled neutronics–fuel behavior calculations in steady state using the Serpent 2 Monte Carlo code

Annals of Nuclear Energy ◽

10.1016/j.anucene.2016.10.015 ◽

2017 ◽

Vol 100 ◽

pp. 50-64 ◽

Cited By ~ 6

Author(s):

Ville Valtavirta ◽

Jaakko Leppänen ◽

Tuomas Viitanen

Keyword(s):

Monte Carlo ◽

Steady State ◽

Monte Carlo Code ◽

Fuel Behavior

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Application of a non-steady-state orbit-following Monte-Carlo code to neutron modeling in the MAST spherical tokamak

Plasma Physics and Controlled Fusion ◽

10.1088/0741-3335/58/10/105005 ◽

2016 ◽

Vol 58 (10) ◽

pp. 105005 ◽

Cited By ~ 8

Author(s):

K Tani ◽

K Shinohara ◽

T Oikawa ◽

H Tsutsui ◽

K G McClements ◽

...

Keyword(s):

Monte Carlo ◽

Steady State ◽

Monte Carlo Code ◽

Spherical Tokamak

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Newly Developed Coupling Scheme in RMC With Internal Thermal Feedback and OTF Doppler-Broadening Method

Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application ◽

10.1115/icone25-66519 ◽

2017 ◽

Cited By ~ 1

Author(s):

Ouwen Yexin ◽

Shanfang Huang ◽

Kan Wang

Keyword(s):

Monte Carlo ◽

Steady State ◽

Cross Section ◽

Large Scale ◽

Nuclear Reactor ◽

Simulation Analysis ◽

Coupling Scheme ◽

Monte Carlo Code ◽

Doppler Broadening ◽

Thermal Hydraulics

RMC (Reactor Monte Carlo)[1] is a self-developed Monte Carlo code for nuclear reactor analysis by Reactor Engineering Analysis Lab (REAL), Tsinghua University. On the basis of the self-developed subchannel module (RMC-TH) and Monte Carlo Cell Tally, the internal coupling interface is developed, which combines both input files to one and realizes the fast mesh correspondence process using the cell expansion technology for repeated structure with thermal-hydraulics feedback. It breaks through the bottleneck of geometrical extensibility for coupled code. On-the-fly Doppler broadening method is adopted as the way to consider the temperature effect on microscopic cross section, which only needs the 0 K cross section library so that the memory cost can be apparently reduced. Steady state simulation analysis are performed on PWR fuel pin and 17×17 assembly model, and the results show the feasibility, accuracy and efficiency of the coupling methodology. Therefore, a promising technology roadmap for the large-scale and geometrically universal nuclear reactor in both steady-state and transient conditions with thermal-hydraulic feedback are established. The roadmap can be further applied to neutronics-thermal-hydraulics-depletion coupling in multi-physics simulation process.

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EFFECT OF ENERGY DEPOSITION MODELLING IN COUPLED STEADY STATE MONTE CARLO NEUTRONICS/THERMAL HYDRAULICS CALCULATIONS

EPJ Web of Conferences ◽

10.1051/epjconf/202124706001 ◽

2021 ◽

Vol 247 ◽

pp. 06001

Author(s):

Riku Tuominen ◽

Ville Valtavirta ◽

Manuel García ◽

Diego Ferraro ◽

Jaakko Leppänen

Keyword(s):

Monte Carlo ◽

Steady State ◽

Power Distribution ◽

Energy Deposition ◽

Computational Time ◽

Test Case ◽

Monte Carlo Code ◽

Thermal Hydraulics ◽

New Treatment ◽

Effective Multiplication

In coupled calculations with Monte Carlo neutronics and thermal hydraulics the Monte Carlo code is used to produce a power distribution which in practice means tallying the energy deposition. Usually the energy deposition is estimated by making a simple approximation that energy is deposited only in fission reactions. The goal of this work is to study how the accuracy of energy deposition modelling affects the results of steady state coupled calculations. For this task an internal coupling between Monte Carlo transport code Serpent 2 and subchannel code SUBCHANFLOW is used along with a recently implemented energy deposition treatment of Serpent 2. The new treatment offers four energy deposition modes each of which offers a different combination of accuracy and required computational time. As a test case, a 3D PWR fuel assembly is modelled with different energy deposition modes. The resulting effective multiplication factors are within 30 pcm. Differences of up to 100K are observed in the fuel temperatures.

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