The challenges associated with high burnup, high temperature and accelerated irradiation for TRISO-coated particle fuel

Maki, John T.; Petti, David A.; Knudson, D. L.; Miller, Gregory K.

doi:10.1016/j.jnucmat.2007.05.019

Cited by 58 publications

(26 citation statements)

References 7 publications

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“…In this concept evaluation we have not done a complete 3-D analysis of the thermal-hydraulic of our core, that will require a 3-D computational fluid dynamic (CFD) modelling of a basic pattern of the core and a 2-D porous media analysis, to get a detailed temperature mapping of the fuel and the coolant. Nevertheless, we believe that safety operation of this pebble bed core is taken for granted as similar studies with higher outlet Helium temperature (1273 K, +50 °C in comparison to our design) (Nickel et al, 2002;Maki et al, 2007;Tálamo et al, 2004) reported fuel temperatures below 1600 K, maximum allowed in this fuel type, even under accidental conditions. The Kugeler-Schulten correlation has been selected for the pressure drop estimation in the porous model of the core.…”

Section: Thermal-hydraulicssupporting

confidence: 59%

Application of gas-cooled Accelerator Driven System (ADS) transmutation devices to sustainable nuclear energy development

Abánades

Garcı́a

García

et al. 2011

Nuclear Engineering and Design

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simultaneous transmutation and hydrogen generation based on a graphite-gas configuration already described in (Abánades and Pérez-Navarro, 2007). Section 2 shows the hydrogen generation and transmutation scheme of the proposed pebble bed device. Section 3 introduces the computational tools used for the neutronic calculations of the device core, benchmarking them with previous existing codes, and the results obtained with those tools. Some radiological discussions regarding our proposal are developed in Section 4. Section 5 analyses the thermal-hydraulics behavior of the device. Finally, in Section 6, these results are used for our concept of the performance of the installation for hydrogen production. Conceptual design of the proposed nuclear based Hydrogen generation scheme

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Section: Thermal-hydraulicssupporting

confidence: 59%

Application of gas-cooled Accelerator Driven System (ADS) transmutation devices to sustainable nuclear energy development

Abánades

Garcı́a

García

et al. 2011

Nuclear Engineering and Design

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“…The amount of fission gases released from the kernel of a TRISO particle depends on temperature, burnup and time [23].…”

Section: Discussionmentioning

confidence: 99%

Microstructure evolution and diffusion of ruthenium in silicon carbide, and the implications for structural integrity of SiC layer in TRISO coated fuel particles

Munthali

Theron

Auret

et al. 2014

Journal of Nuclear Materials

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A thin film of ruthenium(Ru) was deposited on n-type 4H-SiC and 6H-SiC by electron beam deposition technique so as to study interface reaction of ruthenium with silicon carbide at various annealing temperatures, and in two annealing environments namely vacuum and air. The Ru-4H-SiC and Ru-6H-SiC films were both annealed isochronally in a vacuum furnace at temperatures ranging from 500 -1000 o C, and the second set of samples were also annealed in air for temperatures ranging from 100 o C to 600 o C. After each annealing temperature, the films were analysed by Rutherford Backscattering spectrometry (RBS). Raman analysis and x-ray diffraction analysis were also used to analyse some of the samples. RBS analysis of 4H-SiC annealed in a vacuum showed evidence of formation of ruthenium silicide (Ru 2 Si 3 ) and diffusion of Ru into SiC starting from annealing temperature of 700 o C going upwards. In the case of Ru-6H-SiC annealed in a vacuum, RBS analysis showed formation of Ru 2 Si 3 at 600 o C, in addition to the diffusion of Ru into SiC at 800 o C . Raman analysis of the Ru-4H-SiC and Ru-6H-SiC samples that were annealed in a vacuum at 1000 o C showed clear D and G carbon peaks which was evidence of formation of graphite . As for the samples annealed in air ruthenium oxidation started at a temperature of 400 o C and diffusion of Ru into SiC commenced at temperatures of 500 o C for both Ru-4H-SiC and Ru-6H-SiC. X-ray diffraction analysis of samples annealed in air at 600 o C showed evidence of formation of ruthenium silicide in both 4H and 6H-SiC but this was not corroborated by RBS analysis.

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“…Instead, fuel materials damage has been discussed in the 10's of DPA [106]. In the 1980's, the Germans irradiated 50,000 LEU UCO TRISO fuel particles (with 300 µm kernel radius) and no failures were observed after 18-22% FIMA burnups with a fluence of 1.4 − 2.5 × 10 25 n/m 2 [107]. Even so, issues regarding material properties of SiC and this high level of burnup remain [108,109].…”

Section: Structural and Fuel Materials Damagementioning

confidence: 99%

Laser Intertial Fusion Energy: Neutronic Design Aspects of a Hybrid Fusion-Fission Nuclear Energy System

Kramer¹

2010

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This study investigates the neutronics design aspects of a hybrid fusion-fission energy system called the Laser Fusion-Fission Hybrid (LFFH). A LFFH combines current Laser Inertial Confinement fusion technology with that of advanced fission reactor technology to produce a system that eliminates many of the negative aspects of pure fusion or pure fission systems. When examining the LFFH energy mission, a significant portion of the United States and world energy production could be supplied by LFFH plants.The LFFH engine described utilizes a central fusion chamber surrounded by multiple layers of multiplying and moderating media. These layers, or blankets, include coolant plenums, a beryllium (Be) multiplier layer, a fertile fission blanket and a graphite-pebble reflector. Each layer is separated by perforated oxide dispersion strengthened (ODS) ferritic steel walls. The central fusion chamber is surrounded by an ODS ferritic steel first wall. The first wall is coated with 250-500 µm of tungsten to mitigate x-ray damage. The first wall is cooled by Li 17 Pb 83 eutectic, chosen for its neutron multiplication and good heat transfer properties. The Li 17 Pb 83 flows in a jacket around the first wall to an extraction plenum. The main coolant injection plenum is immediately behind the Li 17 Pb 83 , separated from the Li 17 Pb 83 by a solid ODS wall. This main system coolant is the molten salt flibe (2LiF-BeF 2 ), chosen for beneficial neutronics and heat transfer properties. The use of flibe enables both fusion fuel production (tritium) and neutron moderation and multiplication for the fission blanket. A Be pebble (1 cm diameter) multiplier layer surrounds the coolant injection plenum and the coolant flows radially through perforated walls across the bed. Outside the Be layer, a fission fuel layer comprised of depleted uranium contained in Tristructural-isotropic (TRISO) fuel particles having a packing fraction of 20% in 2 cm 1 diameter fuel pebbles. The fission blanket is cooled by the same radial flibe flow that travels through perforated ODS walls to the reflector blanket. This reflector blanket is 75 cm thick comprised of 2 cm diameter graphite pebbles cooled by flibe. The flibe extraction plenum surrounds the reflector bed. Detailed neutronics designs studies are performed to arrive at the described design.The LFFH engine thermal power is controlled using a technique of adjusting the 6 Li/ 7 Li enrichment in the primary and secondary coolants. The enrichment adjusts system thermal power in the design by increasing tritium production while reducing fission. To perform the simulations and design of the LFFH engine, a new software program named LFFH Nuclear Control (LNC) was developed in C++ to extend the functionality of existing neutron transport and depletion software programs. Neutron transport calculations are performed with MCNP5. Depletion calculations are performed using Monteburns 2.0, which utilizes ORIGEN 2.0 and MCNP5 to perform a burnup calculation. LNC supports many design parameters and is capable of p...

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The challenges associated with high burnup, high temperature and accelerated irradiation for TRISO-coated particle fuel

Cited by 58 publications

References 7 publications

Application of gas-cooled Accelerator Driven System (ADS) transmutation devices to sustainable nuclear energy development

Application of gas-cooled Accelerator Driven System (ADS) transmutation devices to sustainable nuclear energy development

Microstructure evolution and diffusion of ruthenium in silicon carbide, and the implications for structural integrity of SiC layer in TRISO coated fuel particles

Laser Intertial Fusion Energy: Neutronic Design Aspects of a Hybrid Fusion-Fission Nuclear Energy System

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