Development of High-Temperature Transport Technologies for Liquid Cadmium in Pyrometallurgical Reprocessing

2009 ◽  
Vol 131 (4) ◽  
Author(s):  
Takatoshi Hijikata ◽  
Tadafumi Koyama
Keyword(s):  
High Temperature ◽  
Fuel Cycle ◽  
Economic Potential ◽  
Test Rig ◽  
Engineering Technology ◽  
Suction Pump ◽  
Suction Tube ◽  
Transport Studies ◽  
Advanced Fuel ◽  
Pyrometallurgical Processing

Pyrometallurgical reprocessing is one of the most promising technologies for the advanced fuel cycle with favorable economic potential and intrinsic proliferation-resistance. The feasibility of pyrometallurgical reprocessing has been studied through many laboratory-scale experiments. Hence the development of the engineering technology necessary for pyrometallurgical reprocessing is a key issue for its industrialization. The development of high-temperature transport technologies for molten salt and liquid cadmium is crucial for pyrometallurgical processing; however, there have been a few transport studies on high-temperature fluids. In this study, a metal transport test rig was installed in an argon glove box with the aim of developing technologies for transporting liquid cadmium at approximately 773 K. The transport of liquid Cd using gravity was controlled by adjusting the valve. The liquid Cd was transported by a suction pump against a 0.93 m head and the transport amount of Cd was well controlled with the Cd amount and the position of the suction tube. The transportation of liquid cadmium at approximately 700 K could be controlled at a rate of 0.5–2.5 dm3/min against a 1.6 m head using a centrifugal pump.

Development of High Temperature Transport Technologies for Molten Salt and Liquid Cadmium in Pyrometallurgical Reprocessing

2008 ◽  
Author(s):  
Takatoshi Hijikata ◽  
Tadafumi Koyama
Keyword(s):  
High Temperature ◽  
Molten Salt ◽  
Centrifugal Pump ◽  
Fuel Cycle ◽  
Salt Transport ◽  
Economic Potential ◽  
Test Rig ◽  
Engineering Technology ◽  
Transport Studies ◽  
Pyrometallurgical Processing

Pyrometallurgical reprocessing technology is currently being focused in many countries for closing actinide fuel cycle because of its favorable economic potential and an intrinsic proliferation-resistant feature due to the inherent difficulty of extracting weapons-usable plutonium. The feasibility of pyrometallurgical reprocessing has been demonstrated through many laboratory scale experiments. Hence the development of the engineering technology necessary for pyrometallurgical reprocessing is a key issue for industrial realization. The development of high-temperature transport technologies for molten salt and liquid cadmium is crucial for pyrometallurgical processing; however, there have been very few transport studies on high-temperature fluids. In this study, a salt transport test rig and a metal transport test rig were installed in an argon glove box with the aim of developing technologies for transporting molten salt and liquid cadmium at approximately 773 K. It was demonstrated that; using a centrifugal pump, molten salt at 773 K could be transported at a controlled rate from 4 to 8 dm3/min against a 1 m head. The transport behavior of the molten salt was found to be similar to that of water, and could be predicted from their similarity of kinematic viscosity. On the other hand, the transportation of liquid cadmium at approximately 700 K could be controlled at a rate of 0.5 to 1.6 dm3/min against a 1.6 m head using the centrifugal pump.

Transport of High-Temperature Molten Salt Slurry for Pyro-Reprocessing

2009 ◽  
Author(s):  
Takatoshi Hijikata ◽  
Tadafumi Koyama
Keyword(s):  
Molten Salt ◽  
Fuel Cycle ◽  
Fission Products ◽  
Spent Fuel ◽  
Supply Tank ◽  
Transport Studies ◽  
Advanced Fuel ◽  
Inner Diameter ◽  
Porous Anode ◽  
Transport Tube

Pyro-reprocessing is one of the most promising technologies for advanced fuel cycle with favorable economic potential and intrinsic proliferation resistance. The development of transport technology for molten salt is a key issue in the industrialization of pyro-reprocessing. As for pure molten LiCl-KCl eutectic salt at approximately 773 K, we have already reported the successful results of transport using gravity and a centrifugal pump. However, molten salt in an electrorefiner mixes with insoluble fines when spent fuel is dissolved in porous anode basket. The insoluble consists of noble metal fission products, such as Pd, Ru, Mo, and Zr. There have been very few transport studies of a molten salt slurry (metal fines - molten salt mixture). Hence, transport experiments on a molten salt slurry were carried out to investigate the behavior of the slurry in a tube. The apparatus used in the transport experiments on a molten salt slurry consisted of a supply tank, a 10° inclined transport tube (10 mm inner diameter), a valve, a filter, and a recovery tank. Stainless steel (SS) fines with diameters from 53 to 415 μm were used. To disperse these fines homogenously, the molten salt and fines were stirred in the supply tank by an impeller at speeds from 1200 to 2100 rpm. The molten salt slurry containing 0.2 to 0.4 vol.% SS fines was transported from the supply tank to the recovery tank through the transportation tube. In the recovery tank, the fines were separated from the molten salt by the filter to measure the transport behavior of molten salt and SS fines. When the velocity of the slurry was 0.02 m/s, only 1% of the fines were transported to the recovery tank. On the other hand, most of the fines were transported when the velocity of the slurry was more than 0.6 m/s. Consequently, the molten salt slurry can be transported when the velocity is more than 0.6 m/s.

Deep Burn Strategy for Pure Reactor-Grade Plutonium in Pebble Bed High Temperature Gas-Cooled Reactors

2008 ◽  
Author(s):  
Eben Mulder ◽  
Dawid Serfontein ◽  
Eberhard Teuchert
Keyword(s):  
High Temperature ◽  
Fuel Cycle ◽  
Waste Incineration ◽  
Β Decay ◽  
Pebble Bed ◽  
Pebble Bed Reactors ◽  
Advanced Fuel ◽  
Very High ◽  
High Temperature Gas

In this article an advanced fuel cycle for pebble bed reactors is introduced that can safely and efficiently incinerate pure reactor-grade Pu [Pu(LWR)], thereby fulfilling the bulk of the GNEP waste incineration requirements. It is shown below that the very high fissile content of the Pu(LWR)-fuel enables it to convert practically all of the 240Pu to 241Pu and incinerate it. Since the fuel contains no 238U, no fresh 239Pu is produced. The 239Pu is reduced in-situ by 99.5% and the 240Pu by 97.6%. The only significant fissile isotope remaining is 241Pu, however, it will decay with a half life of 14.4 years to the fertile 241Am by β-decay.

Analysis of Traction Characteristics of Grease-Lubricated Sliding Bearing

2013 ◽  
Vol 655-657 ◽  
pp. 640-643
Author(s):  
Bo Yuan Yang ◽  
Xiaofan Yan ◽  
Bing Su
Keyword(s):  
High Pressure ◽  
High Temperature ◽  
Room Temperature ◽  
Extreme Pressure ◽  
Test Rig ◽  
Sliding Bearing ◽  
Traction Coefficient ◽  
Lubrication Effect ◽  
Lubricated Sliding

Adopting the test rig of traction characteristics of grease-lubricated sliding bearing, the practical condition of sliding bearing was simulated and the traction coefficient of DGG Grease under different temperature, velocity and load was tested. Besides, the traction characteristics of the grease were also elaborated. The results indicate that the traction coefficient increases when the temperature gradually rises from room temperature while it gradually decreases when the temperature exceeds 85°C. Under the condition of high temperature and high pressure, the extreme pressure additive has obvious effects, the traction coefficient reducing and maintaining constant, so a better lubrication effect is realized.

scholarly journals Advanced Fuel Cycle Cost Basis

2009 ◽  
Author(s):  
D. E. Shropshire ◽  
K. A. Williams ◽  
W. B. Boore ◽  
J. D. Smith ◽  
B. W. Dixon ◽  
...  
Keyword(s):  
Fuel Cycle ◽  
Advanced Fuel

Conceptual Study of Neutron Physics of Nuclear Fuel Cycle for Ceramic Fast Reactor

2021 ◽  
Author(s):  
Xuesong Yan ◽  
Yaling Zhang ◽  
Yucui Gao ◽  
Lei Yang
Keyword(s):  
High Temperature ◽  
Nuclear Fuel ◽  
Fast Reactor ◽  
Spent Nuclear Fuel ◽  
Fuel Cycle ◽  
Fission Products ◽  
Nuclear Fuel Cycle ◽  
Purification Method ◽  
Neutron Physics ◽  
Conceptual Study

Abstract To make the nuclear fuel cycle more economical and convenient, as well as prevent nuclear proliferation, the conceptual study of a simple high-temperature dry reprocessing of spent nuclear fuel (SNF) for a ceramic fast reactor is proposed in this paper. This simple high-temperature dry (HT-dry) reprocessing includes the Atomics International Reduction Oxidation (AIROX) process and purification method for rare-earth elements. After removing the part of fission products from SNF by a HT-dry reprocessing without fine separation, the remaining nuclides and some uranium are fabricated into fresh fuel which can be used back to the ceramic fast reactor. Based on the ceramic coolant fast reactor, we studied neutron physics of nuclear fuel cycle which consists operation of ceramic reactor, removing part of fission products from SNF and preparation of fresh fuels for many time. The parameters of the study include effective multiplication factor (Keff), beam density, and nuclide mass for different ways to remove the fission products from SNF. With the increase in burnup time, the trend of increasing 239Pu gradually slows down, and the trend of 235U gradually decreases and become balanced. For multiple removal of part of fission products in the nuclear fuel cycle, the higher the removal, the larger the initial Keff.

Study on Wear Mechanism of an AlSi–Hexagonal Boron Nitride Abradable Seal Coating

2015 ◽  
Vol 1095 ◽  
pp. 655-661 ◽  
Author(s):  
Tong Liu ◽  
Yue Guang Yu ◽  
Jie Shen ◽  
Jian Ming Liu ◽  
Qiu Yuan Lu
Keyword(s):  
High Temperature ◽  
Wear Mechanism ◽  
Hexagonal Boron Nitride ◽  
Xrd Analysis ◽  
Test Rig ◽  
Speed Test ◽  
Turbine Performance ◽  
Temperature Combustion ◽  
Combustion Region ◽  
High Temperature Combustion

To improve gas turbine performance, it is essential to decrease back flow gases in the high-temperature combustion region of turbo machine by reducing the shroud/rotor gap. An abradable seal coating will function effectively. Therefore, it is significant to identify and characterize the main wear mechanisms occurring on turbo machinery seals. A high temperature and speed test rig has been developed by BGRIMM for testing the AlSi–hBN abradable seal coating and Ti-6Al-4V dummy blade. Impact velocities between 150 and 300m·s-1 and incursion rates between 5.0 and 480 μm·s-1 have been applied. It was found that incursion rate has a greater impact on the wear mechanism of the AlSi–hBN coating, with tests at low incursion rate showing a obvious grooving and little micro-rupture, whereas tests at high incursion rate showing significant cutting and adhesion. The present work also shown that tests at low incursion rate related to a higher IDR, which means that blade suffered a serious wear. The investigation together with SEM and XRD analysis on the coating revealed both wear and adhesion occurred at the end of the test.

Reducing the World's Uranium Requirement by the Thorium Fuel Cycle in High Temperature Reactors

1982 ◽  
Vol 58 (3) ◽  
pp. 414-421 ◽  
Author(s):  
E. Teuchert ◽  
H. J. Rütten ◽  
H. Werner
Keyword(s):  
High Temperature ◽  
Fuel Cycle ◽  
High Temperature Reactors
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