Core neutronics characterization of the GFR2400 Gas Cooled Fast Reactor

Perkó, Zoltán; Pelloni, S.; Mikityuk, Konstantin; Krepel, Jiri; Szieberth, M.; Girardin, G.; Vrban, Branislav; Lüley, Jakub; Čerba, Štefan; Halász, Máté; Fehér, S.; Reiss, T.; Kloosterman, Jan Leen; Stainsby, Richard; Poette, C.

doi:10.1016/j.pnucene.2014.09.016

Cited by 36 publications

(7 citation statements)

References 15 publications

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“…The cladding is an annular cylindrical area that confines the released fission product. The coolant is the outside area with a hexagonal lattice geometry and surrounds the cladding rod 5,6,15 …”

Section: Design and Calculation Methodsmentioning

confidence: 99%

“…The investigation of GFR fuel design has included several considerations of the fuel form binding matrix, that is, coated fuel particles and standard cylindrical fuel rods 2,4 . The recent design of the GFR fuel form is a cylindrical fuel rod in the hexagonal lattice that includes the fuel pellets column, which is surrounded by the gap and cladding 5 . Moreover, the GFR can operate at high temperatures, use helium gas as the primary coolant, and have a low void reactivity effect 3,5 .…”

Section: Introductionmentioning

confidence: 99%

“…The recent design of the GFR fuel form is a cylindrical fuel rod in the hexagonal lattice that includes the fuel pellets column, which is surrounded by the gap and cladding 5 . Moreover, the GFR can operate at high temperatures, use helium gas as the primary coolant, and have a low void reactivity effect 3,5 . The modular GFR potentially uses the natural uranium or depleted uranium fuel, enabling employed closed fuel‐cycle and recycled actinides 4,6,7 .…”

Section: Introductionmentioning

confidence: 99%

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Reflector materials selection for core design of modular gas‐cooled fast reactor using OpenMC code

et al. 2020

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Summary This paper discusses the selection of reflector materials for the core design of modular gas‐cooled fast reactor (GFR). Ideally, the reflector materials can be recycled, compatible with helium as the primary coolant, and resistant to high working temperature in the modular GFR. The modular GFR is a reactor design concept that maintains the criticality to achieve a longer operation time. However, maintaining the neutron population in the fast reactor core is still a challenge due to the high neutron leakage. In this research, the main objective is selecting potential reflectors materials for a modular GFR using open‐source Monte Carlo, OpenMC code. The OpenMC code applied the Monte Carlo method that provides high fidelity three‐dimensional (3D) geometry modeling, implementing continuous energy cross‐sections, and enabling to use of the nuclear data of Evaluated Nuclear Data File (ENDF/B‐VII.b5). The various candidate reflector materials, such as pure nickel, pure magnesium, pure lead, PbO, Ba2Pb, BeO, SiC, and Zr3Si2, are calculated from the neutron physics phenomenon to determine a good neutron reflector. The considered parameters of neutron physics included the multiplication factor profile, neutron energy distribution, flux and fission rate distribution, neutron leakage, core lifetime, mass evolution of fissile and fertile material, and thickness of reflector. The most crucial parameter of GFR core design is determined based on the conditions at the beginning of life (BOL) and the end of life (EOL). Finally, we concluded that the BeO material and silicon‐based materials are good reflector candidates for the core design of modular GFR.

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Section: Design and Calculation Methodsmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

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Reflector materials selection for core design of modular gas‐cooled fast reactor using OpenMC code

et al. 2020

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“…The core is mixed from two zones with different enrichment: the inner core, with lower Table 2. Basic thermal-hydraulic parameters [15]. Figure 2.…”

Section: Description Of Investigated Casementioning

confidence: 99%

“…The description of the homogenization process could be found in the Table 3. Fuel material composition [15]. Table 4.…”

Section: Description Of Investigated Casementioning

confidence: 99%

Coupled Simulation of Gas Cooled Fast Reactor Fuel Assembly With Nestle Code System

Osuský

Čerba

Lüley

et al. 2018

APP

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The paper is focused on coupled calculation of the Gas Cooled Fast Reactor. The proper modelling of coupled neutronics and thermal-hydraulics is the corner stone for future safety assessment of the control and emergency systems. Nowadays, the system and channel thermal-hydraulic codes are accepted by the national regulatory authorities in European Union for license purposes, therefore the code NESTLE was used for the simulation. The NESTLE code is a coupled multigroup neutron diffusion code with thermal-hydraulic sub-channel code. In the paper, the validation of NESTLE code 5.2.1 installation is presented. The processing of fuel assembly homogeneous parametric cross-section library for NESTLE code simulation is made by the sequence TRITON of SCALE code package system. The simulated case in the NESTLE code is one fuel assembly of GFR2400 concept with reflective boundary condition in radial direction and zero flux boundary condition in axial direction. The results of coupled calculation are presented and are consistent with the GFR2400 study of the GoFastR project.

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Core design selection for a long‐life modular gas‐cooled fast reactor using OpenMC code

Raflis

Su’ud

Waris

et al. 2022

Intl J of Energy Research

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This paper discusses design selection with variation of the height-to-diameter (H/D) ratios and core-blanket configuration for a long-life modular gas-cooled fast reactor (GFR). The modular GFR is a nuclear reactor concept that proposes a longer operation time than a traditional nuclear reactor. The potential advantage of GFRs is the expected technological application in electricity, heat processing, nuclear burning, and breeding capability. However, the GFR design still needs an investigation to find the prospective core configuration design. The main objective is to understand the feasible design of long-life modular GFR using the OpenMC code. The OpenMC is an open-source Monte Carlo code that offers the exact solution to solve the neutron transport equation in a high-fidelity model and detailed three-dimensional geometry using Evaluated Nuclear Data File (ENDF/B-VII.1/ V2) nuclear data and continuous energy. The H/D ratios give various core-type, that is, pancake, balance, and tall core, while core-blanket configuration explains different core layouts, that is, homogeneous, radial heterogeneous, and axial heterogeneous. The neutronics parameters characterized are the value of k eff , fission reaction rate, neutron flux, fissile and fertile material, and conversion ratio distribution to know the optimum core design. The study implemented the traditional mesh tallies for the fission reaction rate distribution and the functional expansion tallies (FET) for the flux distribution. The FET feature used the Legendre polynomial for the axial calculation, whereas the Zernike polynomial for the radial calculation. Finally, the balance core-type with homogeneous configuration is the prospective design for advanced research.

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Core neutronics characterization of the GFR2400 Gas Cooled Fast Reactor

Cited by 36 publications

References 15 publications

Reflector materials selection for core design of modular gas‐cooled fast reactor using OpenMC code

Reflector materials selection for core design of modular gas‐cooled fast reactor using OpenMC code

Coupled Simulation of Gas Cooled Fast Reactor Fuel Assembly With Nestle Code System

Core design selection for a long‐life modular gas‐cooled fast reactor using OpenMC code

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