Neutronic Analysis of Thorium Nitride (Th, U233)N Fuel for 500MWth Gas Cooled Fast Reactor (GFR) Long Life without Refueling

Syarifah, Ratna Dewi; Yulianto, Yacobus; Su’ud, Zaki; Basar, Khairul; Irwanto, Dwi

doi:10.4028/www.scientific.net/kem.733.47

Cited by 12 publications

(8 citation statements)

References 10 publications

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“…Previous research has been conducted on neutronic analysis for GFR with thorium nitride fuel using SRAC. Some of the research on GFR using thorium nitride fuel are [14][15][16].…”

Section: Introductionmentioning

confidence: 99%

Neutronic Analysis for The Radial Direction Heterogeneous Core Configuration of GFR with Thorium Fuel

Angelina,

Syarifah,

Widiawati

et al. 2024

J. Phys.: Conf. Ser.

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A neutronic analysis has been carried out for the radial direction heterogeneous core configuration in GFR with thorium nitride fuel to obtain the most optimal heterogeneous design has keff > 1 and excess reactivity below one percent. Neutronic analysis was performed using openMC version 0.13.2 based on open-source Monte Carlo simulation with ENDF/B-VII.1 data library. The first calculation is benchmarking openMC and SRAC where the largest error is 2.49% is caused by different data library. SRAC data library is JENDL 4.0. The second calculation is a homogeneous core configuration with 5% to 15% uranium-U233 fuel variation, the stability lies at 8% for the reference of heterogeneous core configuration. The heterogeneous core configuration was performed with three types of fuel percentage and five different geometry variations. Optimum design for geometry F1:F2:F3 = 1 ring:4 rings:1 ring using fuel type F1:F2:F3 = 6.5%:8%:9.5%. Optimum design for geometry F1:F2:F3 = 2 rings:2 rings:2 rings using fuel type F1:F2:F3 = 7.5%:8%:8.5%. Optimum design for geometry F1:F2:F3= 1 ring:2 rings:3 rings using fuel type F1:F2:F3=7%:8%:9%. Optimum design for geometry F1:F2:F3= 1 ring:3 rings:2 rings using fuel type F1:F2:F3 = 7.5%:8%:8.5%. Optimum design for geometry F1:F2:F3 = 1 ring:1 ring: 4 rings using fuel type F1:F2:F3 = 7.5%:8%:8.5%. The most optimum design among the other five designs is the F1:F2:F3 = 2 rings:2 rings:2 rings geometry design because it has a maximum keff of 1.00999 and excess reactivity of 0.99%. This design is carried out for an extended burn-up 15 years and still stable with the characteristics of the neutron flux and fission rate in this design decrease with burn-up time. Fission product in this design also decreased according to the purpose of the generation IV reactor is the prevention of nuclear weapons.

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“…Previous research has been conducted on neutronic analysis for GFR with thorium nitride fuel using SRAC. Some of the research on GFR using thorium nitride fuel are [14][15][16].…”

Section: Introductionmentioning

confidence: 99%

Neutronic Analysis for The Radial Direction Heterogeneous Core Configuration of GFR with Thorium Fuel

Angelina,

Syarifah,

Widiawati

et al. 2024

J. Phys.: Conf. Ser.

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“…The configuration of the heterogeneous core has a lower neutron flux distribution than the homogeneous core. The resulting fission reaction is more even, thus minimizing the peaking power in the reactor core [11]. However, further studies need to be made for the use of the heterogeneous core with certain variations (more than 2 fuel variations) to produce a more even distribution of neutron flux and a more stable level of criticality (k eff ≈ 1).…”

Section: Introductionmentioning

confidence: 99%

A comparative analysis of gas-cooled fast reactor using heterogeneous core configurations with three and five fuel variations

Prasetya,

Syarifah,

Karomah

et al. 2024

EEJET

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GFR or Gas-cooled Fast Reactor is one type of fast generation-IV that uses a very high cooling temperature. Thus, it is necessary to have the right reactor core design so that the power distribution of neutrons produced reaches a safe and even limit point. The use of a uniform (homogeneous) reactor core can produce peaking power. This is very avoidable because it will cause a reactor accident. In this study, researchers tried to compare the results of the analysis for two heterogeneous reactor core designs including the configuration of 3 fuel variations and 5 fuel variations using UN-PuN fuel. This study aims to determine the keff value produced by both types of fuel variations during 5 years of burn-up and determine the characteristics of neutron flux, fission rate, and fission product during 15 years of burn-up. This study was started by calculating the homogeneous and heterogeneous core of 3 and 5 fuel variations with neutron transport simulation involving OpenMC. The calculation results show that the heterogeneous core configuration of 5 fuel variations for the keff value is more optimal than 3 fuel variations, because it has the smallest excess reactivity value. The neutron flux and fission rate characteristics for 5 fuel variations are more evenly distributed when compared to 3 fuel variations to maintain neutron lifetime and reactor life in operation. Burn-up residual plutonium material and minor actinide waste for 5 fuel variations have less mass than 3 fuel variations. The results of neutronic analysis of GFR reactors with heterogeneous reactor core designs for 5 fuel variations are better in terms of reactor criticality, neutron power distribution, and waste produced. Finally, optimization of the UN-PuN fuel volume fraction of 60 % provides the optimal keff value

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“…Previous research on the addition of minor actinides in the fuel in the Gas-Cooled Fast Reactor (GFR) has been carried out [14][15][16]. The study found that the addition of minor actinides could reduce the k-eff value.…”

Section: Introductionmentioning

confidence: 99%

Neutronics analysis of UN-PuN fuel for 300MW pressurized water reactor using SRAC-COREBN code

et al. 2022

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Nuclear Power Plants (NPP) is one of alternative energy that can be used to replace fossil energy. NPP is a clean energy that doesn't emit CO2 as a residue from the power plant. Pressurized Water Reactor (PWR) is the most widely used commercial reactor to date. This reactor usually uses UO2 as fuel with enrich U-235 and produce plutonium as a waste nuclear. In this study, the fuel uses natural uranium and the addition of plutonium from the spent fuel of PWR, calling it Uranium-Plutonium Nitride (UN-PuN) fuel. Plutonium from spent fuel PWR (U-fueled) consists of Pu-238, Pu-239, Pu-240, Pu-241 and Pu-242, which Pu-239 and Pu-241 are fissile material. The aim of using plutonium is to reduce the amount of nuclear waste and prevent the use of plutonium as a nuclear weapon. The addition of neptunium and protactinium is also carried out in the fuel. Neptunium is one of the minor actinide materials which have high toxicity, so add Np-237 it is very useful to reduce the amount of neptunium in the world. And also, the addition of Np-237 and Pa-231 aims to decrease the keff value both in the Beginning of Life (BOL) and End of Life (EOL) in the reactor. This research calculates the neutronic calculations for PWR use SRAC2006 with COREBN Code and Japanese Evaluated Nuclear Data Library 4.0 (JENDL-4.0) for the nuclear data library. The COREBN code is a calculation method based on interpolation of macroscopic cross-section and finite-difference diffusion theory. The optimum design reached the maximum k-eff value 1.017077 and the maximum power density was 58.47 W/cc. The results obtained are the excess reactivity value of 1.68 % smaller than previous study which produces an excess reactivity value of 11.94 %. So this design has the potential to be applied in the PWR design

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Neutronic Analysis of Thorium Nitride (Th, U233)N Fuel for 500MWth Gas Cooled Fast Reactor (GFR) Long Life without Refueling

Cited by 12 publications

References 10 publications

Neutronic Analysis for The Radial Direction Heterogeneous Core Configuration of GFR with Thorium Fuel

Neutronic Analysis for The Radial Direction Heterogeneous Core Configuration of GFR with Thorium Fuel

A comparative analysis of gas-cooled fast reactor using heterogeneous core configurations with three and five fuel variations

Neutronics analysis of UN-PuN fuel for 300MW pressurized water reactor using SRAC-COREBN code

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