Design Study of Small Modified CANDLE based Long Life Gas Cooled Fast Reactors

Su’ud, Zaki; Miftasani, Fitria; Ilham, Ilham; Sarah, A.; Ariani, Menik; Sekimoto, Hiroshi; Waris, Abdul; Sidik, P

doi:10.1016/j.egypro.2017.09.439

Cited by 13 publications

(10 citation statements)

References 11 publications

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“…One of the approaches to improve reactor fuel efficiency is to innovate the refueling process with a shuffling strategy 9,10 . The aim of this study is to design an SFR that has the ability to operate without refueling 11 for different types of fuels over a long period of time.…”

Section: Introductionmentioning

confidence: 99%

“…This strategy is similar to the breed and burn reactor, also known as a traveling wave reactor (TWR) 13 . Reactor core performance shuffling strategies have also been implemented along the axial, 10 radial, 13‐15 and mixed axial‐radial 9 directions. The burn‐up process of radial fuel shuffling with natural uranium as applied to SFR technologies has been carried out in previous studies for TWRs 13,16 …”

Section: Introductionmentioning

confidence: 99%

“…The effects of neutronic analysis parameters, such as the effective and infinitive multiplication factor, burn‐up levels, conversion ratio, and the density of nuclides, on SFR design with different fuel types (uranium‐plutonium zirconium ([U‐Pu]Zr), uranium‐plutonium nitride ([U‐Pu]N), and mixed oxide (MOX) are investigated. MOX and (U‐Pu)Zr have been studied as SFR fuels, 18 and (U‐Pu)N is deemed the most promising fuel previously used in the simulation of a modified CANDLE reactor 9,19 . Such analysis with varying the fuel types with the modified CANDLE burn‐up shuffling strategy in the radial direction is expected to help identify the optimal type of fuel for the SFR.…”

Section: Introductionmentioning

confidence: 99%

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Neutronic analysis of sodium‐cooled fast reactor design with different fuel types using modified CANDLE shuffling strategy in a radial direction

et al. 2021

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Summary This study compares three fuel types using neutronic analysis for use in a sodium‐cooled fast reactor (SFR) design with a modified CANDLE (Constant Axial shape of Neutron flux, nuclide densities, and power shape During Life of Energy production) radial shuffling strategy. SFR is one type of generation IV reactor that is currently under investigation for commercial implementation. In this study, the SFR design utilizes natural uranium as the fuel input. The designed reactor core has a two‐dimensional cylindrical geometry for each fuel mixed oxide (MOX), uranium‐plutonium nitride ([U‐Pu]N), and uranium‐plutonium zirconium ([U‐Pu]Zr). A radial shuffling strategy, using natural uranium as the fuel input, is applied to the SFR to manage the nuclear fuel burn‐up process of the long‐life reactor. This strategy is called the modified CANDLE burn‐up scheme. The reactor core is divided into 10 regions with equal volume to represent the 10 years that the reactor operates without refueling. Initially, the first (innermost) region of the reactor core is filled with natural uranium fuel. The result of the burn‐up from the first region is then shuffled into the second region. The third region is the result of the burn‐up that is shuffled from the second region, and so on. This mechanism only requires natural uranium as the input for each 10‐year fuel cycle. In this study, the fuel movement scheme is examined for three fuels. Global neutronic parameters, such as the multiplication factors and burn‐up analyses, are observed and optimized. Overall, for an output power of 500 MWth and an active core radius of 110 cm and height of 210 cm, the study indicates that (U‐Pu)N is the optimal fuel to be applied in the SFR with a modified CANDLE burn‐up scheme. (U‐Pu)Zr reaches a critical condition at an output power of 500 MWth with an active core radius of 130 cm and a height of 210 cm; whereas criticality for MOX is achieved at an output power of 1500 MWth with an active core radius of 210 cm and a height of 210 cm.

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Section: Introductionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

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Neutronic analysis of sodium‐cooled fast reactor design with different fuel types using modified CANDLE shuffling strategy in a radial direction

et al. 2021

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“…The modular GFR is attractive because it can handle the decay heat removal passively with the minimum outside intervention so that the reactor operation will be safe. Furthermore, the modular GFR can be exciting and promising because of the less refueling core 8,9 . The modular GFR utilized the hard fast neutron spectrum potential and the nuclear waste minimization without fuel reprocessing and fuel enrichment plants 6‐9 .…”

Section: Introductionmentioning

confidence: 99%

“…Furthermore, the modular GFR can be exciting and promising because of the less refueling core 8,9 . The modular GFR utilized the hard fast neutron spectrum potential and the nuclear waste minimization without fuel reprocessing and fuel enrichment plants 6‐9 . So, it will reduce the obligations of waste and spent fuel management 10 .…”

Section: Introductionmentioning

confidence: 99%

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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Full Core Optimization of Small Modular Gas-Cooled Fast Reactors Using OpenMC Program Code

Ilham

Raflis

Su’ud

2020

J. Phys.: Conf. Ser.

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Indonesia has many small regions and islands with low electrification ratio that needs small power plants. Gas-cooled Fast Reactors (GCFR) is one of the fourth generations of an advanced nuclear power plant with an improved safety system and optimum electricity production that match Indonesia’s energy needs. The neutronic analysis study and optimization of small modular GCFR has been performed with Monte Carlo method OpenMC code that use computational parallelization to speed up calculation time. The full core reactor design is cylindrical with a radius 100 cm and height is 120 cm. Additional 50 cm of radius and 40 cm for the height for the reflector. The core using several types of fuel composed of natural Uranium mixed with spent fuel Plutonium. The variation in fuel fraction pin and percentages of Plutonium in fuel to achieved optimum core design. The design of core reactor has flattened flux and power distribution.

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Design Study of Small Modified CANDLE based Long Life Gas Cooled Fast Reactors

Cited by 13 publications

References 11 publications

Neutronic analysis of sodium‐cooled fast reactor design with different fuel types using modified CANDLE shuffling strategy in a radial direction

Neutronic analysis of sodium‐cooled fast reactor design with different fuel types using modified CANDLE shuffling strategy in a radial direction

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

Full Core Optimization of Small Modular Gas-Cooled Fast Reactors Using OpenMC Program Code

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