A review of TRISO fuel performance models

Powers, Jeffrey J.; Wirth, Brian D.

doi:10.1016/j.jnucmat.2010.07.030

Cited by 157 publications

(73 citation statements)

References 33 publications

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“…(3) Fully ceramic micro-encapsulated (FCM) fuel. FCM fuel consists of TRISO fuel particles embedded in Silicon Carbide (SiC) matrix (Powers and Wirth, 2010). The SiC matrix has good thermal conductivity, can withstand high fast neutron fluence, and is environmentally stable (Terrani et al, 2012).…”

Section: Alternative Fuel Types For the Blanketmentioning

confidence: 99%

Improved resource utilization by advanced burner reactors with breed-and-burn blankets

Zhang

Fratoni

Greenspan

2018

Progress in Nuclear Energy

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A B S T R A C TPrevious studies assessed the feasibility of designing Sodium-cooled Fast Reactors (SFR) in a novel Seed-andBlanket (S&B) configuration in which a significant fraction of the core power is generated by a radial metallic thorium-fueled blanket that operates in the Breed-and-Burn (B&B) mode. The radiation damage on the cladding material in both seed and blanket does not exceed the presently acceptable constraint of 200 Displacements per Atom (DPA). This paper investigates a number of blanket fuel options other than metallic thorium fuel, including thorium dioxide fuel, thorium hydride fuel, thorium nitride Fully Ceramic Encapsulated (FCM) fuel, and Pressurized Water Reactor (PWR) Used Nuclear Fuel (UNF) after limited reprocessing. Since the neutron spectrum of the oxide fueled blanket is softer than that of the reference metallic thorium fueled blanket, it can discharge its fuel at an average burnup of around 110 MWd/kg versus 65 MWd/kg of the metallic thorium. The two thorium hydride fueled blankets feature an even softer neutron spectrum than the oxide fueled blanket and, therefore, a higher average discharge burnup -192 MWd/kg and 245 MWd/kg when the H-to-Th ratio is, respectively, 0.5 and 2.0. The FCM fuel is composed of SiC matrix and cladding that is expected to self-anneal the neutrons induced damage. With the assumption that the FCM fuel will indeed be proven not limited by radiation damage, its discharge burnup could be up to 482 MWd/kg. As a result, the corresponding thorium utilization is the highest of all options examined -close to 80 times the utilization of natural uranium in present Light Water Reactors (LWRs). The amount of Trans-Th isotopes accumulated in the thorium blanket per unit of generated electricity decreases as the blanket fuel is discharged at a higher burnup. Therefore, a higher discharge blanket burnup results in lower long-term radioactivity and radiotoxicity. It is also found that the 232 U/ 233 U ratio in the discharged thorium fuel is over 3 times higher in the thorium hydride than in the other blankets thus improving the thorium-hydride blanket's proliferation resistance. Softening of the blanket spectrum leads to softening of the seed spectrum region interfacing with the blanket and this enables to discharge the seed fuel at a higher average burnup. The higher discharge burnup of the seed fuel reduces the required reprocessing and fuel fabrication capacities per unit of generated electricity. The cores having softer neutron spectrum blankets also feature less positive feedback to sodium voiding and much more negative Doppler coefficient. When PWR UNF is used after limited reprocessing to fuel the blanket, the subcritical blanket driven by the excess neutrons from the seed can discharge this fuel at an average burnup of ∼120 MWd/kg. Combined with the burnup in the first stage PWRs, this two-stage energy system can achieve an accumulated uranium burnup of ∼170 MWd/kg. This increases the fuel utilization of natural uranium by a factor of three relative to oncethroug...

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Section: Alternative Fuel Types For the Blanketmentioning

confidence: 99%

Improved resource utilization by advanced burner reactors with breed-and-burn blankets

Zhang

Fratoni

Greenspan

2018

Progress in Nuclear Energy

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“…Many advanced fuel concepts rely on composite materials. [14][15][16] While for many design and safety analyses the averaged value of thermal conductivity is sufficient, some analyses require spatially resolved measurement of conductivity. This applies to conditions where the exact temperature distribution is critical or where one is tasked with development and validation of model with predictive capability.…”

Section: Measurement Of Thermal Transport a Standard Approaches mentioning

confidence: 99%

Investigation of thermal transport in composites and ion beam irradiated materials for nuclear energy applications

et al. 2016

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Thermal transport in materials used for energy applications is a physical process directly tied to performance and reliability. As a result, a great deal of effort has been devoted to understanding thermal transport in materials whose ability to conduct heat is critical. Here, our objective is to discuss the utility of laser-based thermoreflectance (TR) approaches that provide microscale measurement of thermal transport. We provide several examples that implement the TR technique to investigate thermal transport in materials used in nuclear energy applications. First, we discuss utility of this technique to measure thermal conductivity in ion irradiated ceramic materials during investigations where the primary objective is to understand the impact of radiation induced crystalline structure defects on thermal transport. We also present the capability of TR approach to resolve thermal conductivity of each layer in tristructural isotropic fuel, silicon carbide fiber composites, and 2nd phase precipitates in uranium silicide. Finally, the ability to measure interface thermal resistance between adjacent layers in composites is demonstrated.

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“…Beberapa peneliti telah melakukan penelitian untuk reaktor HTGR, antara lain tentang teras reaktor HTGR merujuk pada pustaka [10,11,12,13,14,15,16] , juga pene-litian tentang bahan bakar TRISO oleh peneliti sesuai pustaka [17,18,19] . Penelitian lain juga melakukan penelitian tentang keselamatan reaktor HTGR yaitu Zuhair dan kawan-kawan mengenai efek kecelakaan water ingress pada reaktor HTGR sesuai pustaka [20] .…”

Section: Pendahuluanunclassified

Analisis Inventori Reaktor Daya Eksperimental Jenis Reaktor Gas Temperatur Tinggi

Kuntjoro

Udiyani

2016

urania

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ABSTRAK ANALISIS INVENTORI REAKTOR DAYA EKSPERIMENTAL JENIS REAKTOR GAS TEMPERATUR TINGGI.Berkaitan dengan rencana Badan Tenaga Nuklir Nasional (BATAN) untuk mengoperasikan reaktor eksperimental jenis Reaktor Gas Temperatur Tinggi (RGTT), maka diperlukan analisis keselamatan terhadap reaktor terutama yang berkaitan dengan issue lingkungan. Analisis sebaran radionuklida dari reaktor ke lingkungan pada kondisi operasi normal atau abnormal diawali dengan estimasi sumber radionuklida di teras reaktor (inventori teras) berdasarkan pada tipe, daya, dan operasi reaktor. Tujuan penelitian adalah melakukan analisis inventori teras untuk disain Reaktor Daya Eksperimental (RDE) jenis reaktor gas temperature tinggi berdaya 10 MWt, 20 MWt dan 30 MWt. Analisis dilakukan menggunakan program ORIGEN2 berbasis pustaka penampang lintang pada temperatur tinggi. Perhitungan diawali dengan membuat modifikasi beberapa parameter pustaka tampang lintang berdasarkan temperatur rata-rata teras sebesar 5700 °C dan dilanjutkan dengan melakukan perhitungan inventori reaktor untuk reaktor RDE berdaya 10 MWt. Parameter utama reaktor RDE 10 MWt yang digunakan dalam perhitungan sama dengan parameter utama reaktor HTR-10. Setelah inventori reaktor RDE 10 MWt diperoleh, dilakukan perbandingan dengan hasil dari peneliti terdahulu. Berdasarkan kesesuaian hasil yang didapat dilakukan desain untuk reaktor RDE 20MWEt dan 30 MWt untuk memperoleh parameter utama reaktor tersebut berupa jumlah bahan bakar pebble bed di teras reaktor, tinggi dan diameter teras. Berdasarkan pareameter utama teras dilakukan perhitungan inventori teras RDE 20 MWt dan 30 MWt dengan metode yang sama dengan metode perhitungan pada RDE 10 MWt. Hasil yang diperoleh adalah inventori terbesar untuk reaktor RDE 10 MWt, 20 MWt dan 30 MWt secara berurutan untuk kelompok Kr adalah sekitar 1,00E+15 Bq, 1,20E+16 Bq, 1,70E+16 Bq untuk kelompok I sebesar 6,50E+16 Bq, 1,20E+17 Bq, 1,60E+17 Bq dan untuk kelompok Cs sebesar 2,20E+16 Bq, 2,40E+16 Bq dan 2,60E+16 Bq. Inventori teras selanjutnya akan digunakan untuk menghitung suku sumber dari reaktor yang akan digunakan sebagai dasar untuk perhitungan sebaran radionuklida ke lingkungan.

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A review of TRISO fuel performance models

Cited by 157 publications

References 33 publications

Improved resource utilization by advanced burner reactors with breed-and-burn blankets

Improved resource utilization by advanced burner reactors with breed-and-burn blankets

Investigation of thermal transport in composites and ion beam irradiated materials for nuclear energy applications

Analisis Inventori Reaktor Daya Eksperimental Jenis Reaktor Gas Temperatur Tinggi

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