Fuel processing

1990 ◽  
Vol 331 (1619) ◽  
pp. 381-393
Keyword(s):  
Fuel Cycle ◽  
Process Intensification ◽  
Economic Feasibility ◽  
Reactor Performance ◽  
Fuel Processing ◽  
Technical Requirements ◽  
Fuel Design ◽  
Irradiation Performance ◽  
Plutonium Fuel ◽  
Generating System

The technical and economic viability of the fast breeder reactor as an electricity generating system depends not only upon the reactor performance but also on a capability to recycle plutonium efficiently, reliably and economically through the reactor and fuel cycle facilities. Thus the fuel cycle is an integral and essential part of the system. Fuel cycle research and development has focused on demonstrating that the challenging technical requirements of processing plutonium fuel could be met and that the sometimes conflicting requirements of the fuel developer, fuel fabricator and fuel reprocessor could be reconciled. Pilot plant operation and development and design studies have established both the technical and economic feasibility of the fuel cycle but scope for further improvement exists through process intensification and flowsheet optimization. These objectives and the increasing processing demands made by the continuing improvement to fuel design and irradiation performance provide an incentive for continuing fuel cycle development work.

Application of Sonic Nozzle in Unsteady Flow Rate Generating System for Compressible Fluid

2014 ◽  
Vol 496-500 ◽  
pp. 703-706
Author(s):  
Xiao Xin Wang ◽  
Tao Wang ◽  
Jun Zheng Wang
Keyword(s):  
Unsteady Flow ◽  
Flow Rate ◽  
Compressible Fluid ◽  
Control Method ◽  
Open Loop ◽  
Inlet Flow ◽  
Sonic Nozzle ◽  
Technical Requirements ◽  
Inlet Flow Rate ◽  
Generating System

To meet the requirement of unsteady flow rate generating system for compressible fluid, an inlet flow rate control method with sonic nozzle is proposed. When inlet flow rate is known, feedback of unsteady flow rate can be obtained by an isothermal tank. A proper sonic nozzle is designed according to the technical requirements, and the flow rate is calculated. Open loop experiments are carried out on generating system with and without sonic nozzle. The results indicate that influence of downstream on upstream can be greatly reduced by the designed sonic nozzle, and accurate feedback of unsteady flow rate is ensured.

A Study of Transverse Buckling Effect on the Characteristics of Nuclides Burnup Wave in a Fast Neutron Multiplying Media

2019 ◽  
Vol 5 (4) ◽  
Author(s):  
Manish Kumar ◽  
Om Pal Singh
Keyword(s):  
Fast Neutron ◽  
Fuel Cycle ◽  
Fuel Burnup ◽  
Full Width ◽  
Half Maximum ◽  
Transient Time ◽  
Velocity Of Propagation ◽  
Neutron Leakage ◽  
Uranium Plutonium ◽  
Plutonium Fuel

A study of transverse buckling effect on the characteristics of nuclides burnup wave in multiplying media (cylindrical geometry) has been carried out. The burnup wave is characterized in terms of velocity of propagation, transient length (TL), and transient time (TT) in establishing the burnup wave and full width at half maximum (FWHM) in the established region of the wave. The uranium–plutonium fuel cycle is considered. The sensitivity of the results is studied for different radial buckling led leakage of neutrons. It is discovered that the velocity of the wave increases with the increase in the radius of the cylinder (i.e., reduction in the transverse buckling and hence increase in radial neutron leakage). FWHM is relatively insensitive to radial neutron leakage. The transient time and transient length are very large for smaller radius; these decrease with the increase in radius. The study provides insight on the build-up of burnup wave in the neutron multiplying media and brings out the importance of transverse buckling led radial neutron leakage on the characteristics of fuel burnup wave in multiplying media.

scholarly journals Thoria-Based Cermet Nuclear Fuel: Neutronics Fuel Design and Fuel Cycle Analysis

2002 ◽  
Author(s):  
Thomas J. Downar ◽  
Sean M. McDeavitt ◽  
S. T. Revankar ◽  
A. A. Solomon ◽  
T. K. Kim
Keyword(s):  
Nuclear Fuel ◽  
Metal Matrix ◽  
Fuel Cycle ◽  
Performance Model ◽  
Fuel Cycles ◽  
Fuel Cycle Analysis ◽  
Research Initiative ◽  
Fuel Design ◽  
Water Reactors ◽  
Analysis Of Dispersion

Cermet nuclear fuels have significant potential to enhance fuel performance because of low internal fuel temperatures and low stored energy. The combination of these benefits with the inherent proliferation resistance, high burnup capability, and favorable neutronic properties of the thorium fuel cycle provide intriguing options for using thoria based cermet nuclear fuel in advanced nuclear fuel cycles. This paper describes aspects of a Nuclear Energy Research Initiative (NERI) project with two primary goals: (1) Evaluate the feasibility of implementing the thorium fuel cycle in existing or advanced reactors using a zirconium-matrix cermet fuel, and (2) Develop enabling technologies required for the economic application of this new fuel form. The following paper will first describe the fuel thermal performance model developed for the analysis of dispersion metal matrix fuels. The model will then be applied to the design and analysis of thorium/uranium/zirconium metal matrix fuel pins for light water reactors using neutronic simulation methods.

scholarly journals Multiple Tier Fuel Cycle Studies for Waste Transmutation

2002 ◽  
Author(s):  
R. N. Hill ◽  
T. A. Taiwo ◽  
J. A. Stillman ◽  
D. J. Graziano ◽  
D. R. Bennett ◽  
...  
Keyword(s):  
Mass Flow ◽  
System Performance ◽  
Fuel Cycle ◽  
Department Of Energy ◽  
Waste Streams ◽  
Fuel Processing ◽  
Advanced Fuel ◽  
Support Ratio ◽  
Plutonium Separation ◽  
The U.S

As part of the U.S. Department of Energy Advanced Accelerator Applications Program, a systems study was conducted to evaluate the transmutation performance of advanced fuel cycle strategies. Three primary fuel cycle strategies were evaluated: dual-tier systems with plutonium separation, dual-tier systems without plutonium separation, and single-tier systems without plutonium separation. For each case, the system mass flow and TRU consumption were evaluated in detail. Furthermore, the loss of materials in fuel processing was tracked including the generation of new waste streams. Based on these results, the system performance was evaluated with respect to several key transmutation parameters including TRU inventory reduction, radiotoxicity, and support ratio. The importance of clean fuel processing (∼0.1% losses) and inclusion of a final tier fast spectrum system are demonstrated. With these two features, all scenarios capably reduce the TRU and plutonium waste content, significantly reducing the radiotoxicity; however, a significant infrastructure (at least 1/10 the total nuclear capacity) is required for the dedicated transmutation system.

scholarly journals Partitioning and transmutation contribution of MYRRHA to an EU strategy for HLW management and main achievements of MYRRHA related FP7 and H2020 projects: MYRTE, MARISA, MAXSIMA, SEARCH, MAX, FREYA, ARCAS

2020 ◽  
Vol 6 ◽  
pp. 33
Author(s):  
Hamid Aït Abderrahim ◽  
Peter Baeten ◽  
Alain Sneyers ◽  
Marc Schyns ◽  
Paul Schuurmans ◽  
...  
Keyword(s):  
Waste Management ◽  
Nuclear Power ◽  
Power Plants ◽  
Fuel Cycle ◽  
Economic Feasibility ◽  
Potential Contribution ◽  
Spent Fuel ◽  
Geological Disposal ◽  
Deep Geological Disposal ◽  
Partitioning And Transmutation

Today, nuclear power produces 11% of the world's electricity. Nuclear power plants produce virtually no greenhouse gases or air pollutants during their operation. Emissions over their entire life cycle are very low. Nuclear energy's potential is essential to achieving a deeply decarbonized energy future in many regions of the world as of today and for decades to come, the main value of nuclear energy lies in its potential contribution to decarbonizing the power sector. Nuclear energy's future role, however, is highly uncertain for several reasons: chiefly, escalating costs and, the persistence of historical challenges such as spent fuel and radioactive waste management. Advanced nuclear fuel recycling technologies can enable full use of natural energy resources while minimizing proliferation concerns as well as the volume and longevity of nuclear waste. Partitioning and Transmutation (P&T) has been pointed out in numerous studies as the strategy that can relax constraints on geological disposal, e.g. by reducing the waste radiotoxicity and the footprint of the underground facility. Therefore, a special effort has been made to investigate the potential role of P&T and the related options for waste management all along the fuel cycle. Transmutation based on critical or sub-critical fast spectrum transmuters should be evaluated in order to assess its technical and economic feasibility and capacity, which could ease deep geological disposal implementation.

Northern Sea Route: Modern State and Challenges

2014 ◽  
Author(s):  
Nataliya Marchenko
Keyword(s):  
Oil And Gas ◽  
Chukchi Sea ◽  
Lessons Learned ◽  
Economic Feasibility ◽  
Asia Pacific ◽  
Russian Arctic ◽  
The North ◽  
Technical Requirements ◽  
Northern Sea Route ◽  
Ice Conditions

It is well-known that navigating the waterway from the primary trade hubs in northern Europe to the Asia-Pacific ports and contrariwise along the Russian Arctic Coast (Northern Sea Route - NSR) is much shorter and faster, than southern ways via Suez or around Africa. The NSR can significantly save costs (through saving time and fuel) and avoids the risk of attack by pirates. In addition, an increase in oil and gas activity in the North, forecasts of global warming and an ice-free Arctic have stimulated interest in Arctic navigation. However, Arctic transportation poses significant challenges because of the heavy ice conditions that exist during both the winter and summer. The profitability of using the NSR is called into question if possible high tariffs are included in the cost estimates. For many years, the NSR was principally used for internal Russian transport and since the end of the 1980s up until 2010, it was in stagnation with total amount of cargo transported annually stood at less than two million tons. Important political decisions in the 90s and increased economic feasibility intensified traffic and freight turnover. In 2013, the NSR Administration (NSRA) was established, new rules for navigation were approved and tariff policies were modified. In 2013, the NSRA issued 635 permits to sail in NSR waters, and 71 transit voyages have since been completed. The total amount of transit cargo was 1.36 million tons. More than 40% of the total number of permits were issued to vessels without ice class [1] according to the Russian Maritime Register of Shipping [2]. There are strong technical requirements for vessels attempting to sail the NSR; regardless, several accidents occurred in 2012–2013. Two vessels were dented by ice in the Chukchi Sea in 2012. A tanker was holed in September 2013 and created a real danger of an ecological disaster from fuel leakage for several days. Despite the expectation of an ice-free Arctic, the ice conditions in 2013 were rather difficult, and the Vilkitsky Strait (a key strait in the NSR between the Kara and Laptev seas) was closed by ice for almost the entire navigation period. In this paper, we review the current situation in the Russian Arctic, including political and administrative actions, recent accidents and the associated conditions and lessons learned.

Hydrogen Production for Fuel Cells by a Methane Reformer Integrated with Steam Generation

2012 ◽  
Vol 10 (1) ◽  
Author(s):  
Donglai Xie ◽  
Ang Peng ◽  
Ziliang Wang ◽  
Yajun Zhang
Keyword(s):  
Hydrogen Production ◽  
Natural Gas ◽  
Steam Reforming ◽  
Space Velocity ◽  
Processing Unit ◽  
Reactor Performance ◽  
Steam Generation ◽  
Fuel Processing ◽  
Oxidative Reforming ◽  
Oxidation Reactor

The fuel cell based heat and power co-generation is considered to be well qualified for a distributed energy system for residential and small commercial applications. A kW-scale system is under development in the New Energy Group in South China University of Technology. Natural gas is selected as fuel for hydrogen production. The system mainly consists of a fuel processing unit, a power generation unit and an auxiliary unit. The fuel processing unit includes a reformer (integrated with steam generation), two high and low temperature shift reactors, and a preferential oxidation reactor. The reformer integrated with steam generation is designed to produce hydrogen-rich syngas from natural gas and water. It can be operated under steam methane reforming or oxidative steam reforming modes. 800 grams of commercial nickel catalyst supported on gamma alumina are loaded in the reformer. The reactor performances under typical steam reforming and oxidative reforming modes are tested. Influences of reaction temperature, steam-to-carbon ratio and methane space velocity on reactor performance under steam reforming mode are experimentally investigated. Influences of oxygen-to-carbon ratio, steam-to-carbon ratio and methane space velocity on reactor performance under oxidative reforming mode are also studied. The reformer will be integrated with the other parts of the system to build a complete system.

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