Becoming the Nuclear-Front-End

2017 ◽  
Vol 47 (189) ◽  
Author(s):  
Patrick Schukalla
Keyword(s):  
Nuclear Reactor ◽  
Chemical Elements ◽  
High Technology ◽  
Power Production ◽  
Uranium Mining ◽  
Nuclear Industry ◽  
Current State ◽  
Front End ◽  
Production And Consumption ◽  
Uranium Exploration

Uranium mining often escapes the attention of debates around the nuclear industries. The chemical elements’ representations are focused on the nuclear reactor. The article explores what I refer to as becoming the nuclear front – the uranium mining frontier’s expansion to Tanzania, its historical entanglements and current state. The geographies of the nuclear industries parallel dominant patterns and the unevenness of the global divisions of labour, resource production and consumption. Clearly related to the developments and expectations in the field of atomic power production, uranium exploration and the gathering of geological knowledge on resource potentiality remains a peripheral realm of the technopolitical perceptions of the nuclear fuel chain. Seen as less spectacular and less associated with high-technology than the better-known elements of the nuclear industry the article thus aims to shine light on the processes that pre-figure uranium mining by looking at the example of Tanzania.

scholarly journals History of buildingand operation of the Nizhny Tulom hydroelectric power plant on the Kola Peninsula.

2020 ◽  
Vol 11 (7-2020) ◽  
pp. 19-32
Author(s):  
Olga E. Konovalova ◽  
◽  
Nikolai M. Kuznetsov ◽  
Keyword(s):  
Hydroelectric Power Plant ◽  
Hydroelectric Power Station ◽  
Hydroelectric Power ◽  
Power Station ◽  
Construction Time ◽  
Current State ◽  
Production And Consumption ◽  
Great Patriotic War ◽  
History Of ◽  
The Cost

The article tells the story of the creation of the Nizhne-Tulomskaya hydroelectric power station (HPP). The main energy parameters of the hydroelectric power station, the layoutof the main structures of the station, and archival photos of the construction time are given. Data on the production and consumption of electricity for own needs, the cost of 1 kW·h during the great Patriotic war are shown. It is told about the reconstruction and current state of the station.

Detection of an unknown emission source in the Baltic Sea using the new oceanographic tracer U-233/U-236

2021 ◽  
Author(s):  
Karin Hain ◽  
Ala Aldahan ◽  
Mats Eriksson ◽  
Robin Golser ◽  
Gideon M. Henderson ◽  
...  
Keyword(s):  
Baltic Sea ◽  
Nuclear Weapons ◽  
Nuclear Power ◽  
Global Fallout ◽  
Power Production ◽  
Nuclear Industry ◽  
Chemical Fractionation ◽  
The Baltic Sea ◽  
The Baltic ◽  
Nuclear Power Production

<p><span>By analysing the two long-lived anthropogenic Uranium (U) isotopes U-233 and U-236 in different compartments </span><span>of the environment affected by releases of nuclear power production or by global fallout from nuclear weapons tests</span><span>, we showed that the corresponding isotopic ratios U-233/U-236</span><span> differ by one order of magnitude. Based on these experimental results which were obtained with the ultra-sensitive detection method Accelerator Mass Spectrometry, we suggested a representative ratio for nuclear weapons fallout of </span><span>U-233/U-236</span><span> =</span><span> (1.40 ± 0.15) ·10</span><sup><span>-2</span></sup><span> and (0.12 ± 0.01) ·10</span><sup><span>-2</span></sup><span> for releases from nuclear power production. Consequently, the </span><span>U-233/U-236</span><span> ratio not only </span><span>has the potential to become a novel sensitive fingerprint for releases from nuclear industry, but could also serve as a powerful oceanographic tracer due to the conservative behaviour of U in ocean water which does not suffer from chemical fractionation. </span></p><p><span>As a first application of this paired tracer, we studied the distribution of U-233 and U-236 concentrations in addition to I-129 in the Baltic Sea which is known to have received inputs of radionuclides from various contamination sources including the two European reprocessing plants, global fallout from weapons testings and fallout from the Chernobyl accident. Our data indicate an additional unidentified source of reactor U-236 in the Baltic Sea demonstrating the high sensitivity of the U-233/U-236 ratio to distinguish different emission sources in water mixing processes.</span></p>

Shaping Mega-Science Projects and Practical Steps for Success

2018 ◽  
pp. 5690-5704
Author(s):  
Phil Crosby
Keyword(s):  
Project Management ◽  
Large Scale ◽  
High Technology ◽  
Engineering Science ◽  
Front End ◽  
Science Projects ◽  
Start Up ◽  
Successful Design

Too many large engineering/science projects fail in terms of budget overruns, schedule slippage, or under-performance, and this has profound implications not only for the construction and commissioning organisations, but also for the funders (public or private), and the clients or users. Successful design and delivery is therefore not only a commercial necessity but also a societal imperative. Success in complex mega-projects is not easily achieved and is interpreted differently by various stakeholders, moreover there is growing recognition of the importance of front-end shaping. In this chapter, the author addresses the inception, planning and feasibility phases of complex mega-projects in some depth, based on extant and updated research of large scale high-technology science projects. Five key success drivers are explained, and when addressed together, are shown to be especially potent. This chapter draws out subtle aspects of mega-project management shown to be crucial at the preliminary, or start-up, phase.

Intelligent Transformer: Possibilities and Challenges

2011 ◽  
Vol 29 (1) ◽  
pp. 95-100 ◽  
Author(s):  
Beldjajev Viktor ◽  
Roasto Indrek ◽  
Lehtla Tõnu
Keyword(s):  
Energy Management ◽  
Low Frequency ◽  
Power Production ◽  
Future Trends ◽  
Advantages And Disadvantages ◽  
Autonomous Networks ◽  
Production And Consumption ◽  
Wide Range ◽  
The Future

Intelligent Transformer: Possibilities and Challenges This paper covers the concept of an intelligent transformer that is a good candidate to replace a conventional low frequency transformer in the microgrids. As the power production and consumption can vary in a wide range, the new substations have to meet many requirements to guarantee reliable energy management in the autonomous networks. Different topologies of intelligent transformers can be used to meet these requirements. Therefore the advantages and disadvantages of the existing topologies were analyzed. The future trends and challenges are also discussed.

Study of the Influence of Microstructure and Intergranular Carbides on the Oxidation Behavior of a Nickel Base Alloy 690 TT in Supercritical Water Nuclear Reactor Conditions

2020 ◽  
Author(s):  
Alberto Sáez-Maderuelo ◽  
María Luisa Ruiz-Lorenzo ◽  
Francisco Javier Perosanz ◽  
Patricie Halodová ◽  
Jan Prochazka ◽  
...  
Keyword(s):  
Supercritical Water ◽  
Nuclear Power ◽  
Power Plants ◽  
Oxidation Behavior ◽  
Nuclear Reactor ◽  
Base Alloy ◽  
Nuclear Industry ◽  
Operating Conditions ◽  
Alloy 690 ◽  
Reactor Operating

Abstract Alloy 690, which was designed as a replacement for the Alloy 600, is widely used in the nuclear industry due to its optimum behavior to stress corrosion cracking (SCC) under nuclear reactor operating conditions. Because of this superior resistance, alloy 690 has been proposed as a candidate structural material for the Supercritical Water Reactor (SCWR), which is one of the designs of the next generation of nuclear power plants (Gen IV). In spite of this, striking results were found [1] when alloy 690 was tested without intergranular carbides. These results showed that, contrary to expectations, the crack growth rate is lower in samples without intergranular carbides than in samples with intergranular carbides. Therefore, the role of the carbides in the corrosion behavior of Alloy 690 is not yet well understood. Considering these observations, the aim of this work is to study the effect of intergranular carbides in the oxidation behavior (as a preliminary stage of degenerative processes SCC) of Alloy 690 in supercritical water (SCW) at two temperatures: 400 °C and 500 °C and 25 MPa. Oxide layers of selected specimens were studied by different techniques like Scanning Electron Microscope (SEM) and Auger Electron Spectroscopy (AES).

scholarly journals Front-end Design and Characterization for the ν-Angra Nuclear Reactor Monitoring Detector

2016 ◽  
Vol 11 (07) ◽  
pp. P07018-P07018 ◽  
Author(s):  
T.I. Dornelas ◽  
F.T.H. Araújo ◽  
A.S. Cerqueira ◽  
J.A. Costa ◽  
R.A. Nóbrega
Keyword(s):  
Nuclear Reactor ◽  
Front End

Development of Experimental Setup of High Temperature Helium Loop and Preparation for In-Pile Operation

2013 ◽  
Author(s):  
Marija Miletić ◽  
Rostislav Fukač ◽  
Igor Pioro ◽  
Alexey Dragunov
Keyword(s):  
High Temperature ◽  
Nuclear Power ◽  
Fossil Fuels ◽  
Nuclear Reactor ◽  
Fuel Cycle ◽  
Strong Dependence ◽  
Nuclear Industry ◽  
Research Centre ◽  
Experimental Setup ◽  
Creep Tests

Rapidly increasing energy and electricity demands, global concerns over the climate changes and strong dependence on foreign fossil fuels supplies are powerfully influencing greater use of nuclear power. In order to establish the viability of next-generation reactor concepts to meet tomorrow’s needs for clean and reliable energy production the fundamental research and development issues need to be addressed for the Generation-IV nuclear-energy systems. Generation-IV reactor concepts are being developed to use more advanced materials, coolants and higher burn-ups fuels, while keeping a nuclear reactor safe and reliable. One of the six Generation-IV concepts which will utilize thermal neutron spectrum is a Very High Temperature Reactor (VHTR). This reactor concept uses a graphite-moderated core with a once-through uranium fuel cycle, using high temperature helium as the coolant. Because helium is naturally inert and single-phase, the helium-cooled reactor can operate at much higher temperatures, leading to higher efficiency. Current VHTR concepts will use fuels such as uranium dioxide, uranium carbide, or uranium oxycarbide. Since some of these fuels are new in nuclear industry and due to their unknown properties and behaviour within VHTR conditions it is very important to address these issues by investigate their characteristics within conditions close to those in VHTRs. This research can be performed in a research reactor with in-pile helium loop designed and constructed in Research Centre Rez, Ltd. The purpose of the High Temperature Helium Loop (HTHL) is to simulate technical and chemical conditions of VHTR’s coolant. The loop is intended to serve an as experimental device for fatigue and creep tests of construction metallic materials for gas-cooled reactors and it should be also employed for research in field of gaseous coolant chemistry. The loop will serve also for tests of nuclear graphite, dosing and Helium purification systems. Because the VHTR is a new reactor concept, major technical uncertainties remain relative to helium-cooled advanced reactor systems. This paper summarizes the concept of the HTHL in the Research Centre Rez Ltd., its design, utilization and future plans for experimental setup.

Decommissioning of Nuclear Reactor Systems

1992 ◽  
Vol 206 (4) ◽  
pp. 273-280 ◽  
Author(s):  
J H Large
Keyword(s):  
Waste Disposal ◽  
Nuclear Power ◽  
First Generation ◽  
Nuclear Reactor ◽  
Nuclear Industry ◽  
Radioactive Waste Disposal ◽  
Lost Generation ◽  
Power Stations ◽  
Safety Case ◽  
Generation Capacity

The decision-making process involving the decommissioning of the British graphite-moderated, gas-cooled Magnox power stations is complex. There are timing, engineering, waste disposal, cost and lost generation capacity factors and the ultimate uptake of radiation dose to consider and, bearing on all of these, the overall decision of when and how to proceed with decommissioning may be heavily weighed by political and public tolerance dimensions. These factors and dimensions are briefly reviewed with reference to the ageing Magnox nuclear power stations, of which Berkeley and Hunterston A are now closed down and undergoing the first stages of decommissioning and Trawsfynydd, although still considered as available capacity, has had both reactors closed down since February 1991 and is awaiting substantiation and acceptance of a revised reactor pressure vessel safety case. Although the other first-generation Magnox power stations at Hinkley Point, Bradwell, Dungeness and Sizewell are operational, it is most doubtful that these stations will be. able to eke out a generating function for much longer. It is concluded that the British nuclear industry has adopted a policy of deferred decommissioning, that is delaying the process of complete dismantlement of the radioactive components and assemblies for at least one hundred years following close-down of the plant. In following this option the nuclear industry has expressed considerable confidence that the decommissioning technology required will he developed with passing time, that acceptable radioactive waste disposal methods and facilities will be available and that the eventual costs of decommissioning will not escalate without restraint.

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