Power flattening on modified CANDLE small long life gas-cooled fast reactor

Monado, Fiber; Su’ud, Zaki; Waris, Abdul; Basar, Khairul; Ariani, Menik; Sekimoto, Hiroshi

doi:10.1063/1.4895859

Cited by 8 publications

(4 citation statements)

References 3 publications

(3 reference statements)

Supporting

Mentioning

Contrasting

Unclassified

Order By: Relevance

“…The calculation is use SRAC2006 code both PIJ calculation and CITATION calculation. The SRAC2006 is designed and developed by JAERI (Japan Atomic Energy Research Institute), now called JAEA [6]. The data libraries use JENDL 4.0.…”

Section: Design Concept and Calculation Methodsmentioning

confidence: 99%

See 1 more Smart Citation

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

Syarifah

Yulianto

Su’ud

et al. 2017

KEM

Self Cite

View full text Add to dashboard Cite

Neutronic analysis of Thorium Nitride (Th, U233)N fuel of 500MWth Gas Cooled Fast Reactor (GFR) has been done. In this study the neutronic analysis use SRAC2006 code both PIJ and CITATION calculation. The data libraries use JENDL 4.0. First calculation is survey parameter with U-233 enrichment variation. From the homogeneous core configuration calculation, when the enrichment of U-233 is 8.2%, the maximum k-eff value is 1,00819 with excess reactivity value 0,812%. The average power density is 63 Watt/cc and the maximum power density 100 Watt/cc. The heterogeneous core configuration calculation has been done to flattening the power of the reactor. The variation fuel of F1:F2:F3 = 7.8%:8%:8.8%. The fraction of fuel : cladding: coolant = 60%:10%:30%. The max k-eff value of heterogeneous core configuration is 1,01229 with excess reactivity value 1.21%. The average power density is 65 Watt/cc and the maximum power density 92 Watt/cc. The power density distribution of heterogeneous core configuration is flatter than homogeneous core configuration.

show abstract

Section: Design Concept and Calculation Methodsmentioning

confidence: 99%

“…Helium is chemical inert, single phase, and low neutron moderation [2]. Beforehand, neutronic analysis of GFR with SRAC Code and modified CANDLE burn up scheme has been analyze [3,4,5,6].…”

Section: Introductionmentioning

confidence: 99%

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

Syarifah

Yulianto

Su’ud

et al. 2017

KEM

Self Cite

View full text Add to dashboard Cite

show abstract

“…Nilai k-eff yang diperoleh pada awal siklus adalah sekitar 1,0490 (kondisi kritis) dengan ekses reaktivitas sebesar 0,0468 setelah itu meningkat secara monoton hingga akhir siklus (k-eff = 1,0598). Nilai k-eff yang diperoleh diawal operasi ini mempunyai margin yang lebih besar jika dibandingkan dengan nilai k-eff (k-eff = 1,01075) yang diperoleh oleh Monado (Monado, 2014) pada desain konsep GFR berpendingin helium. Nilai-nilai ini menandakan populasi neutron dari waktu ke waktu tetap terjaga dalam keadaan yang memenuhi syarat untuk sebuah teras reaktor nuklir dapat terus beroperasi.…”

Section: Hasil Dan Diskusiunclassified

Desain Konseptual Teras Reaktor Cepat Berumur Panjang Berpendingin S-CO2 dengan Bahan Bakar Uranium Metalik Alam

Darmawati

Ariani

Monado

2020

JFU

Self Cite

View full text Add to dashboard Cite

Telah dibuat sebuah desain konsep teras reaktor cepat berpendingin S-CO2 dengan bahan bakar uranium metalik alam yang dapat beroperasi dalam waktu yang lama (berumur panjang). Metode penyusunan bahan bakar dilakukan menggunakan strategi burn-up modified CANDLE (Constant Axial shape of Neutron flux, nuclide densities and power shape During Life of Energy production). Strategi pembakaran CANDLE yang dimodifikasi dengan region pertama berada di dekat region terakhir telah diterapkan. Perhitungan teras reaktor dilakukan menggunakan modul CITATION pada sistem kode SRAC (Standard Reactor Analysis Code). Tahap awal penelitian dengan menghitung sel bahan bakar menggunakan modul PIJ sebagai input siklus telah dilakukan. Parameter perhitungan yang diamati adalah nilai faktor multiplikasi efektif (k-eff), distribusi daya arah aksial dan radial serta reaktivitas pada teras reaktor. Hasil perhitungan menunjukkan nilai k-eff dari awal siklus pembakaran sekitar 1,0490 hingga akhir siklus sebesar 1,0598. Distribusi daya arah aksial paling besar terjadi pada ketinggian teras 115 cm yaitu sebesar 1,9824 watt/cc. Sedangkan untuk distribusi daya arah radial paling besar terjadi di tengah teras yaitu sebesar 2,1697 watt/cc. Nilai reaktivitas rata-rata selama waktu operasi sebesar 0,0562. Berdasarkan hasil tersebut, keadaan teras reaktor memenuhi syarat untuk beroperasi. The conceptual design of a fast reactor core has been made with S-CO2 as a coolant and natural metallic uranium as a fuel, which can operate for a long time (long-life reactor). The fuel preparation method uses a strategy of burn-up modified CANDLE (Constant Axial shape of Neutron flux, nuclide density, and power shape During Life of Energy production). The modified CANDLE burning strategy with the first region near the last region has been implemented. The reactor core calculation is performed using the CITATION module on the SRAC (Standard Reactor Analysis Code) code system. The initial phase of research by counting fuel cells using the PIJ module as a cycle input has been carried out. The calculation parameters observed were effective multiplication factor (k-eff), axial and radial power distribution, and reactivity on the reactor core. The calculation results show the k-eff value from the burning of life (BOL) cycle around 1.0490 until the end of the cycle of 1.0598. The largest axial power distribution occurs at the reactor core height of 115 cm, equal to 1.9824 watts/cc, whereas the largest radial power distribution occurs in the center of the core, which is equal to 2.1697 watts/cc. The average reactivity value during the operation time of around 0.0562. Based on these results, the reactor core condition qualifies for operation.

show abstract

“…Gas Cooled Fast Reactor (GFR), Lead Cooled Fast Reactor (LFR), Molten Salt Reactor (MSR), Sodium Cooled Fast Reactor (SFR), Supercritical Water Cooled Reactor (SCWR), and Very High Temperature Reactor (VHTR) [2]. Beforehand, neutronics analysis of GFR with SRAC Code and modified CANDLE burn up scheme with uranium natural has been analyzed [3,4,5,6].…”

Section: Introductionmentioning

confidence: 99%

Design Study of 200MWth Gas Cooled Fast Reactor with Nitride (UN-PuN) Fuel Long Life without Refueling

et al. 2016

Self Cite

View full text Add to dashboard Cite

Power flattening on modified CANDLE small long life gas-cooled fast reactor

Cited by 8 publications

References 3 publications

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

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

Desain Konseptual Teras Reaktor Cepat Berumur Panjang Berpendingin S-CO2 dengan Bahan Bakar Uranium Metalik Alam

Design Study of 200MWth Gas Cooled Fast Reactor with Nitride (UN-PuN) Fuel Long Life without Refueling

Contact Info

Product

Resources

About