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 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 Np-237 incineration study in various beams in ADS setup QUINTA

Nukleonika ◽  
2018 ◽  
Vol 63 (1) ◽  
pp. 17-22 ◽  
Author(s):  
Stanisław Kilim ◽  
Elżbieta Strugalska-Gola ◽  
Marcin Szuta ◽  
Marcin Bielewicz ◽  
Sergej I. Tyutyunnikov ◽  
...  
Keyword(s):  
Fission Product ◽  
Proton Beam ◽  
Neutron Capture ◽  
Gamma Ray ◽  
Fission Products ◽  
Neutron Field ◽  
Gamma Ray Spectrometry ◽  
Driven System ◽  
Accelerator Driven System

Abstract Neptunium-237 samples were irradiated in a spallation neutron field produced in accelerator-driven system (ADS) setup QUINTA. Five experiments were carried out on the accelerators at the JINR in Dubna - one in carbon (C6+), three in deuteron, and one in a proton beam. The energy in carbon was 24 GeV, in deuteron 2, 4 and 8 GeV, respectively, and 660 MeV in the proton beam. The incineration study method was based on gamma-ray spectrometry. During the analysis of the spectra several fission products and one actinide were identified. Fission product activities yielded the number of fissions. The actinide (Np-238), a result of neutron capture by Np-237, yielded the number of captures. The main goal of this work was to find out if and how the incineration rate depended on parameters of the accelerator beam.

The Cumulative Beta Decay and the Effect of Electron Radiation on a Simulated HLW Sintered Glass

1997 ◽  
Vol 506 ◽  
Author(s):  
A.M. Bevilacqua ◽  
N.B. Messi de Bernasconi ◽  
D.O. Russo ◽  
S. Prastalo ◽  
M. Sanfilippo ◽  
...  
Keyword(s):  
Heavy Metal ◽  
Beta Decay ◽  
Internal Conversion ◽  
Fission Products ◽  
Electron Radiation ◽  
Spent Fuel ◽  
Sintered Glass ◽  
Computer Codes ◽  
The Mean ◽  
High Level

The first aim of the work was to calculate, by means of the computer codes ORIGEN2. 1, ITS 3.0 and TRIM95, the beta/gamma cumulative dose and displacements produced by the fission products hold in the high level wastes (HLW) from reprocessed CANDU spent fuel, up to one million years, with a burnup of 7,000 MWd/tU and a cooling time of 20 years. Based on that results were calculated and graphically presented the mean electron energy (β−, internal conversion and Auger) and the cumulative beta events and ionization dose due to electrons, per metric ton of heavy metal and per cubic centimeter of the sintered HLW glass form, as a function of the time up to one million year.

Numerical Modeling of EM Pump Efficiency

2006 ◽  
Author(s):  
Daniel P. Cook ◽  
Yitung Chen ◽  
Lillian J. Ratliff ◽  
Huajun Chen ◽  
Jian Ma
Keyword(s):  
Numerical Study ◽  
Beam Power ◽  
Liquid Lead ◽  
Pump Efficiency ◽  
Operational Parameters ◽  
Pump Design ◽  
Driven System ◽  
Analytic Expressions ◽  
Accelerator Driven System ◽  
Low Efficiency

The pilot Molten lead-bismuth target circuit (TC-1) in University of Nevada, Las Vegas (UNLV) was designed for beam power of 1 MW accelerator driven system (ADS). The TC-1 is a liquid lead-bismuth eutectic (LBE) circulation loop. Circulation of the liquid alloy is driven by an annular linear induction pump (ALIP). Experimental measurements of system parameters have yielded a surprisingly low pump efficiency of less than 1%. A numerical study of the pump efficiency has been conducted to determine which operational parameters are responsible for this low efficiency and to give insight into future EM pump design. The numerical study has entailed incorporating algorithms which calculated the EM body force into a commercial CFD code (FEMLab). The EM body forces were calculated using both simplified analytic expressions, as well as by numerical solution of Maxwell's equations.

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 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 Analysis of the Accelerator-Driven System Fuel Assembly during the Steam Generator Tube Rupture Accident

Materials ◽  
2021 ◽  
Vol 14 (8) ◽  
pp. 1818
Author(s):  
Di-Si Wang ◽  
Bo Liu ◽  
Sheng Yang ◽  
Bin Xi ◽  
Long Gu ◽  
...  
Keyword(s):  
Fuel Assembly ◽  
Steam Generator ◽  
Metal Flow ◽  
Maximum Temperature ◽  
Steam Generator Tube ◽  
Driven System ◽  
Fuel Assemblies ◽  
Accelerator Driven System ◽  
The Impact ◽  
Steam Bubble

China is developing an ADS (Accelerator-Driven System) research device named the China initiative accelerator-driven system (CiADS). When performing a safety analysis of this new proposed design, the core behavior during the steam generator tube rupture (SGTR) accident has to be investigated. The purpose of our research in this paper is to investigate the impact from different heating conditions and inlet steam contents on steam bubble and coolant temperature distributions in ADS fuel assemblies during a postulated SGTR accident by performing necessary computational fluid dynamics (CFD) simulations. In this research, the open source CFD calculation software OpenFOAM, together with the two-phase VOF (Volume of Fluid) model were used to simulate the steam bubble behavior in heavy liquid metal flow. The model was validated with experimental results published in the open literature. Based on our simulation results, it can be noticed that steam bubbles will accumulate at the periphery region of fuel assemblies, and the maximum temperature in fuel assembly will not overwhelm its working limit during the postulated SGTR accident when the steam content at assembly inlet is less than 15%.

Experimental benchmarks on kinetic parameters in accelerator-driven system with 100 MeV protons at Kyoto University Critical Assembly

2017 ◽  
Vol 105 ◽  
pp. 346-354 ◽  
Author(s):  
Cheol Ho Pyeon ◽  
Masao Yamanaka ◽  
Tomohiro Endo ◽  
Willem Fredrik G. van Rooijen ◽  
Go Chiba
Keyword(s):  
Kinetic Parameters ◽  
Critical Assembly ◽  
Driven System ◽  
Accelerator Driven System ◽  
Mev Protons
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