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.

scholarly journals Study of a conceptual accelerator driven system loaded with thorium dioxide mixed with transuranic dioxides in TRISO particles

2016 ◽  
Vol 31 (3) ◽  
pp. 197-206 ◽  
Author(s):  
Gizem Bakir ◽  
Gamze Genc ◽  
Huseyin Yapici
Keyword(s):  
Target Material ◽  
High Energy ◽  
Monte Carlo Code ◽  
Spent Fuel ◽  
Thorium Dioxide ◽  
Pure Lead ◽  
Driven System ◽  
Accelerator Driven System ◽  
Triso Particles ◽  
Fuel Particles

Nuclear spent fuel management is one of the top major subjects in the utilization of nuclear energy. Hence, solutions to this problem have been increasingly researched in recent years. The basic aim of this work is to examine the fissile breeding and transuranic fuel transmutation potentials of a gas cooled accelerator-driven system. In line with this purpose, firstly, the conceptually designed system is optimized by using several target materials and fuel mixtures, from the point of neutronic. Secondly, three different material compositions, namely, pure lead bismuth eutectic (LBE), LBE+natural UO2, and LBE+15 % enrichment UO2, are considered as target material. The target zone is separated to two sub-zones but as one within the other. The outer sub-zone is pure LBE target, and the inner sub-zone is either UO2 or pure LBE target. The UO2 target sub-zone is cooled with helium gas. Finally, the thorium dioxide mixed with transuranic dioxides, discharged from PWR-MOX spent fuel, in pebbles composed of graphite and TRISO-coated spherical fuel particles, is used for breeding fissile fuel and transmuting transuranic fuels. Three different thorium-transuranic mixtures, (Th, Pu)O2, (Th, Cm)O2, (Th, Pu, MA)O2, are examined with various mixture fractions. The packing fractions of the fuel pebbles in the transmutation core and the tristructural-isotropic coated fuel particles in a pebble are assumed as 60 % and 29 %, respectively. The transmutation core is also cooled with a high-temperature helium coolant. In order to produce high-flux neutrons that penetrate through the transmutation core, the target is exposed to the continuous beams of 1 GeV protons. The computations have been carried out with the high-energy Monte Carlo code MCNPX using the LA150 library. The numerical outcomes show that the examined accelerator-driven system has rather high neutronic data in terms of the energy production and fissile fuel breeding.

scholarly journals Transmutations of Long-Lived and Medium-Lived Fission Products Extracted from CANDU and PWR Spent Fuels in an Accelerator-Driven System

2019 ◽  
Vol 2019 ◽  
pp. 1-13
Author(s):  
Alper Buğra Arslan ◽  
İlayda Yilmaz ◽  
Gizem Bakir ◽  
Hüseyin Yapici
Keyword(s):  
Fission Products ◽  
Time Dependent ◽  
Thermal Reactor ◽  
Beam Power ◽  
Spent Fuel ◽  
Driven System ◽  
Helium Gas ◽  
Computer Codes ◽  
Accelerator Driven System ◽  
Additional Fuel

This study presents the time-dependent analyses of transmutations of long-lived fission products (LLFPs) and medium-lived fission products (MLFPs) occurring in thermal reactors in a conceptual helium gas-cooled accelerator-driven system (ADS). In accordance with this purpose, the CANDU-37 and PWR 15 × 15 spent fuels are separately considered. The ADS consists of LBE-spallation neutron target, subcritical fuel zone, and graphite reflector zone. While the considered ADS is fueled with the spent nuclear fuels extracted from each thermal reactor without the use of additional fuel, fission products extracted from same thermal reactor are also placed into transmutation zone in graphite reflector zone. The LLFP transmutation performance of the modified ADS is analyzed by considering three different spent fuels extracted from the thermal reactors. Spent fuels are extracted from CANDU-37 in case A, from PWR-15 × 15 in case B, and from CANDU-37 fueled with mixture of PWR 15 × 15 spent fuel and 46% ThO2 in case C. The LBE target is bombard with protons of 1000 MeV. The proton beam power is assumed as 20 MW, which corresponds to 1.24828·1017 protons per second. MCNPX 2.7 and CINDER 90 computer codes are used for the time-dependent burn calculations. The ADS is operated under subcritical mode until the value of keff increases to 0.984, and the maximum operation times are obtained as 3400, 3270, and 5040 days according to the spent fuel cases of A, B, and C, respectively. The calculations bring out that in the modified ADS, LLFPs and MLFPs, which are extracted from thermal reactors, can be transformed to stable isotopes in significant amounts along with energy production.

scholarly journals Study of an ADS Loaded with Thorium and Reprocessed Fuel

2012 ◽  
Vol 2012 ◽  
pp. 1-12 ◽  
Author(s):  
Graiciany de Paula Barros ◽  
Claubia Pereira ◽  
Maria A. F. Veloso ◽  
Antonella L. Costa
Keyword(s):  
Nuclear Fuel ◽  
Monte Carlo Code ◽  
Spent Fuel ◽  
Fuel Rods ◽  
Driven Systems ◽  
The Core ◽  
Combined Use ◽  
Driven System ◽  
Accelerator Driven System ◽  
Accelerator Driven Systems

Accelerator-driven systems (ADSs) are investigated for long-lived fission product transmutation and fuel regeneration. The aim of this paper is to investigate the nuclear fuel evolution and the neutronic parameters of a lead-cooled accelerator-driven system used for fuel breeding. The fuel used in some fuel rods wasT232hO2forU233production. In the other fuel rods was used a mixture based upon Pu-MA, removed from PWR-spent fuel, reprocessed by GANEX, and finally spiked with thorium or depleted uranium. The use of reprocessed fuel ensured the use ofT232hO2without the initial requirement ofU233enrichment. In this paper was used the Monte Carlo code MCNPX 2.6.0 that presents the depletion/burnup capability, combining an ADS source and kcode-mode (for criticality calculations). The multiplication factor (keff) evolution, the neutron energy spectra in the core at BOL, and the nuclear fuel evolution during the burnup were evaluated. The results indicated that the combined use ofT232hO2and reprocessed fuel allowedU233production without the initial requirement ofU233enrichment.

scholarly journals RADIATION DAMAGE IN URANIUM TARGET OF THE ACCELERATOR DRIVEN SYSTEM “KIPT NEUTRON SOURCE”

2021 ◽  
pp. 24-28
Author(s):  
V.V. Gann ◽  
A.V. Gann ◽  
B.V. Borts ◽  
I.M. Karnaukhov ◽  
A.A. Parkhomenko
Keyword(s):  
Radiation Damage ◽  
Neutron Source ◽  
High Energy ◽  
Neutron Production ◽  
High Energy Electrons ◽  
Driven System ◽  
Accelerator Driven System ◽  
Uranium Target ◽  
Main Input

In this work, the rate of radiation damage production in a uranium target of the neutron source at NSC KIPT un-der electrons irradiation with an energy of 100 MeV was estimated. The contribution of elastic and inelastic proc-esses is determined: high-energy electrons and gamma quanta, photo-neutron production, fragments arising from photo-fission, damage from neutrons. It was found that the main input into damage production in a uranium target give fragments of photo-fission.

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.

A HR-SEM Investigation of the Microstructure of PBMR Test Fuel Particles

2008 ◽  
Author(s):  
N. G. van der Berg ◽  
J. B. Malherbe ◽  
A. J. Botha
Keyword(s):  
High Temperature ◽  
South African ◽  
Nuclear Fission ◽  
Pebble Bed ◽  
Fission Power ◽  
Triso Particles ◽  
Fuel Particles ◽  
Sem Investigation ◽  
High Temperature Gas ◽  
Test Fuel

There is currently renewed interest in high temperature nuclear fission power reactors. The Pebble Bed Modular Reactor (PBMR) is one of several high temperature gas-cooled reactors being investigated by researchers. The South African design of the PBMR is based on the original German design, with the fuel particles (called TRISO particles) being small multilayer spheres.

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