scholarly journals Medical Radioisotope Production in a Power-Flattened ADS Fuelled with Uranium and Plutonium Dioxides

2016 ◽  
Vol 2016 ◽  
pp. 1-11 ◽  
Author(s):  
Gizem Bakır ◽  
Saltuk Buğra Selçuklu ◽  
Hüseyin Yapıcı
Keyword(s):  
Power Density ◽  
Density Ratio ◽  
Target Material ◽  
Fuel Mixture ◽  
Carbon Composite ◽  
Production Performance ◽  
Radioisotope Production ◽  
Spent Fuel ◽  
Medical Radioisotope ◽  
Fission Power

This study presents the medical radioisotope production performance of a conceptual accelerator driven system (ADS). Lead-bismuth eutectic (LBE) is selected as target material. The subcritical fuel core is conceptually divided into ten equidistant subzones. The ceramic (natural U, Pu)O2fuel mixture and the materials used for radioisotope production (copper, gold, cobalt, holmium, rhenium, thulium, mercury, palladium, thallium, molybdenum, and yttrium) are separately prepared as cylindrical rods cladded with carbon/carbon composite (C/C) and these rods are located in the subzones. In order to obtain the flattened power density, percentages of PuO2in the mixture of UO2and PuO2in the subzones are adjusted in radial direction of the fuel zone. Time-dependent calculations are performed at 1000 MW thermal fission power (Pth) for one hour using the BURN card. The neutronic results show that the investigated ADS has a high neutronic capability, in terms of medical radioisotope productions, spent fuel transmutation and energy multiplication. Moreover, a good quasiuniform power density is achieved in each material case. The peak-to-average fission power density ratio is in the range of 1.02–1.28.

scholarly journals Time-Dependent Neutronic Analysis of a Power-Flattened Gas Cooled Accelerator Driven System Fuelled with Thorium, Uranium, Plutonium, and Curium Dioxides TRISO Particles

2016 ◽  
Vol 2016 ◽  
pp. 1-11 ◽  
Author(s):  
Gizem Bakır ◽  
Gamze Genç ◽  
Hüseyin Yapıcı
Keyword(s):  
Power Density ◽  
High Energy ◽  
Time Dependent ◽  
Monte Carlo Code ◽  
Spent Fuel ◽  
Driven System ◽  
Accelerator Driven System ◽  
Fission Power ◽  
Triso Particles ◽  
Fuel Particles

This study presents the power flattening and time-dependent neutronic analysis of a conceptual helium gas cooled Accelerator Driven System (ADS) loaded with TRISO (tristructural-isotropic) fuel particles. Target material is lead-bismuth eutectic (LBE). ThO2, UO2, PuO2, and CmO2TRISO particles are used as fuel. PuO2and CmO2fuels are extracted from PWR-MOX spent fuel. Subcritical core is radially divided into 10 equidistant subzones in order to flatten the power produced in the core. Tens of thousands of these TRISO fuel particles are embedded in the carbon matrix fuel pebbles as five different cases. The high-energy Monte Carlo code MCNPX 2.7 with the LA150 library is used for the neutronic calculations. Time-dependent burnup calculations are carried out for thermal fission power (Pth) of 1000 MW using the BURN card. The energy gain of the ADS is in the range of 99.98–148.64 at the beginning of a cycle. Furthermore, the peak-to-average fission power density ratio is obtained between 1.021 and 1.029 at the beginning of the cycle. These ratios show a good quasi-uniform power density for each case. Furthermore, up to 155.1 g233U and 103.6 g239Pu per day can be produced. The considered system has a high neutronic capability in terms of energy multiplication, fissile breeding, and spent fuel transmutation with thorium utilization.

Medical Cyclotrons

2009 ◽  
Vol 02 (01) ◽  
pp. 133-156 ◽  
Author(s):  
D. L. Friesel ◽  
T. A. Antaya
Keyword(s):  
Cancer Therapy ◽  
Scientific Research ◽  
High Energy ◽  
Industrial Applications ◽  
Medical Applications ◽  
Particle Accelerators ◽  
Radioisotope Production ◽  
Practical Applications ◽  
Medical Radioisotope ◽  
High Energy Particles

Particle accelerators were initially developed to address specific scientific research goals, yet they were used for practical applications, particularly medical applications, within a few years of their invention. The cyclotron's potential for producing beams for cancer therapy and medical radioisotope production was realized with the early Lawrence cyclotrons and has continued with their more technically advanced successors — synchrocyclotrons, sector-focused cyclotrons and superconducting cyclotrons. While a variety of other accelerator technologies were developed to achieve today's high energy particles, this article will chronicle the development of one type of accelerator — the cyclotron, and its medical applications. These medical and industrial applications eventually led to the commercial manufacture of both small and large cyclotrons and facilities specifically designed for applications other than scientific research.

scholarly journals Recent development of Supercapacitor Electrode Based on Carbon Materials

2019 ◽  
Vol 8 (1) ◽  
pp. 35-49 ◽  
Author(s):  
Zhenhui Li ◽  
Ke Xu ◽  
Yusheng Pan
Keyword(s):  
Carbon Nanotube ◽  
Power Density ◽  
Carbon Materials ◽  
High Specific Capacitance ◽  
Carbon Foam ◽  
Carbon Composite ◽  
Carbon Cloth ◽  
Supercapacitor Electrode ◽  
Review State

Abstract Supercapacitor has gained significant attention due to its fast charging/discharging speed, high power density and long-term cycling stability in contrast to traditional batteries. In this review, state-of-the-art achievements on supercapacitor electrode based on carbon materials is summarized. In all-carbon composite materials part, various carbon materials including graphene, carbon nanotube, carbon foam and carbon cloth are composited to fabricate larger specific surface area and higher electrical conductivity electrodes. However, obstacles of low power density as well as low cycling life still remain to be addressed. In metal-oxide composites part, carbon nanotube, graphene, carbon fiber fabric and hollow carbon nanofibers combine with MnO2 respectively, which significantly address drawbacks of all-carbon material electrodes. Additionally, TiO2 is incorporated into graphene electrode to overcome the low mechanical flexibility of graphene. In organic active compounds part, conducting polymers are employed to combinate with carbon materials to fabricate high specific capacitance, long-term thermal stability and outstanding electroconductivity flexible textile supercapacitors. In each part, innovation, fabrication process and performance of the resulting composites are demonstrated. Finally, future directions that could enhance the performance of supercapacitors are discussed.

scholarly journals Charged-Particle Cross Section Database for Medical Radioisotope Production

2002 ◽  
Vol 39 (sup2) ◽  
pp. 1282-1285 ◽  
Author(s):  
Syed M. Qaim ◽  
Ferenc T. Tárkányi ◽  
Pavel Obložinský ◽  
Khunab Gul ◽  
Alex Hermanne ◽  
...  
Keyword(s):  
Charged Particle ◽  
Cross Section ◽  
Radioisotope Production ◽  
Medical Radioisotope

scholarly journals Minimize fission power peaking factor in radial direction of water-cooled and water-moderated thermionic conversion reactor core

2018 ◽  
Vol 4 (1) ◽  
pp. 7-11
Author(s):  
Pavel A. Alekseev ◽  
Aleksei D. Krotov ◽  
Mikhail K. Ovcharenko ◽  
Vladimir A. Linnik
Keyword(s):  
Power Density ◽  
Hexagonal Lattice ◽  
Reactor Core ◽  
The Core ◽  
Intermediate Neutron ◽  
Density Factor ◽  
Fission Power ◽  
Concentric Circles ◽  
Thermionic Conversion ◽  
Fuel Elements

The paper investigates the possibility for reducing the radial power peaking factor kr inside the core of a water-cooled water-moderated thermionic converter reactor (TCR). Due to a highly nonuniform power density, the TCR generates less electric power and the temperature increases in components of the thermionic fuel elements, leading so to a shorter reactor life. A TCR with an intermediate neutron spectrum has its thermionic fuel elements (TFE) arranged inside the core in concentric circles, this providing for a nonuniform TFE spacing and reduces kr. The water-cooled water-moderated TCR under consideration has a much larger number of TFEs arranged in a hexagonal lattice with a uniform pitch. Power density flattening in a core with a uniform-pitch lattice can be achieved, e.g., through using different fuel enrichment in core or using additional in-core structures. The former requires different TFE types to be taken into account and developed while the latter may cause degradation of the reactor neutronic parameters; all this will affect the design’s economic efficiency. It is proposed that the core should be split into sections with each section having its own uniform lattice pitch which increases in the direction from the center to the periphery leading so to the radial power density factor decreasing to 1.06. The number of the sections the core is split into depends on the lattice pitch, the TFE type and size, the reflector thickness, and the reactor design constraints. The best lattice spacing options for each section can be selected using the procedure based on a genetic algorithm technology which allows finding solutions that satisfy to a number of conditions. This approach does not require the reactor dimensions to be increased, different TFE types to be taken into account and developed, or extra structures to be installed at the core center.

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