Forefront of Nuclear Reactor Decommissioning—Toward Fukushima Dai-ichi NPS Decommissioning—Status and Issues for Technology Development

2018 ◽  
Vol 138 (8) ◽  
pp. 518-521
Author(s):  
Toru OGAWA
Keyword(s):  
Nuclear Reactor ◽  
Technology Development

Status of Future Reactor Technology Development in Korea

2010 ◽  
Author(s):  
Dohee Hahn ◽  
Yeong-Il Kim ◽  
Yong Wan Kim
Keyword(s):  
Nuclear Reactor ◽  
Technology Development ◽  
Atomic Energy Commission ◽  
Development Plan ◽  
Reactor Technology ◽  
Very High Temperature Reactor ◽  
Demonstration Plant ◽  
High Temperature Reactor ◽  
Consistent Direction

In order to provide a consistent direction to long-term R&D activities, the Korea Atomic Energy Commission (KAEC) approved a long-term development plan for future nuclear reactor systems which include sodium cooled fast reactor (SFR) and very high temperature reactor (VHTR) on December 22, 2008. The SFR system is regarded as a promising technology to perform actinide management. The final goal of the long-term SFR development plan is the construction of an advanced SFR demonstration plant by 2028. The nuclear hydrogen project in Korea aims at designing and constructing a nuclear hydrogen demonstration system by 2022 to demonstrate its hydrogen production capability. This paper summarizes the overall long-term project plans for SFR and VHTR technology development and explains results of detailed design studies with supporting R&D activities.

Using Scenarios to Evaluate Technology Development Options for Power Generation Equipment

2006 ◽  
Author(s):  
Flavio J. Franco
Keyword(s):  
Power Generation ◽  
Power Systems ◽  
Gas Turbines ◽  
Nuclear Reactor ◽  
Technology Development ◽  
Thermal Power ◽  
Primary Energy ◽  
Energy Sources ◽  
Power Generation Equipment

The world of power generation is currently facing a number of challenges and uncertainties, caused by technical, economic, political, geographical and social factors. Manufacturers of power generation equipment have to design their strategies for technology development taking into account these challenges and uncertainties. They have to set goals for the medium and the long term, which involve the commitment of huge amounts of resources. At the same time, given the uncertainty of the future, they have to try to reduce their risks. Scenario-Based Planning is a methodology to deal with uncertainty in making decisions for the long term. It does not tell planners what will probably happen but helps them to understand what may happen through an understanding of the relationships of cause and effect within the environment of interest. Taking gas turbines as an example, this paper shows an application of the method to the evaluation of the markets related to different primary energy sources and different technologies, within power generation scenarios given by the IEA and scenarios proposed in previous papers by the author. Although current power generation gas turbines are predominantly designed to burn natural gas, developments based on other primary energy sources will require gas turbines to run with different fuels (synthetic gas or hydrogen, for example), helium or CO2 (in high temperature nuclear reactor systems) or hot air (in hybrid solar thermal power systems). Wind power may also require backup from gas turbines, probably incorporating significant fuel flexibility. An estimate of the value of the potential markets related to these different applications of gas turbines is made in this paper. Historical and estimated experience curves for the technologies of interest and their dependence relationships are used in this analysis, with a system dynamics model as described in [1].

Experimental Activity for the Investigation of Mixing and Thermal Stratification Phenomena in the CIRCE Pool Facility

2016 ◽  
Author(s):  
D. Martelli ◽  
M. Tarantino ◽  
I. Di Piazza
Keyword(s):  
Fast Reactor ◽  
Thermal Stratification ◽  
Nuclear Reactor ◽  
Technology Development ◽  
Safety Issue ◽  
Natural Circulation ◽  
Fundamental Aspect ◽  
Horizon 2020 ◽  
Fuel Bundle ◽  
Gen Iv

Since the Lead-cooled Fast Reactor (LFR) has been conceptualized in the frame of GEN IV International Forum (GIF), ENEA is strongly involved in the HLM technology development. In particular, several experimental campaign employing HLM loop and pool facilities (CIRCE [1], NACIE [2], HELENA [3], HERO [4]) are carried out in order to support HLM technologies development. In this frame, suitable experiments were carried out on the CIRCE pool facility refurbished with the Integral Circulation Experiment (ICE) test section in order to investigate the thermal hydraulics and the heat transfer in grid spaced Fuel Pin Bundle cooled by liquid metal providing, among the others aim, experimental data in support of codes validation for the European fast reactor development. The study of thermal stratification in large pool reactor is relevant in the design of HLM nuclear reactor especially for safety issue. Thermal stratification should induce thermomechanical stresses on the structures and in accidental scenario conditions, could opposes to the establishment of natural circulation which is a fundamental aspect for the achievements of safety goals required in the GEN-IV roadmap. In the present work, a Protected Loss of Heat Sink with Loss Of Flow (PLOHS+LOF) scenario is experimentally simulated and the mixed convection with thermal stratification phenomena is investigated during the simulated transient, as foreseen in the frame of Horizon 2020 SESAME project [5]. A full characterization of thermal stratification inside the pool is presented, and the main results gained during the run are reported. The two tests named A (20 h) and B (6 h) here reported, essentially differs for the power supplied to the fuel bundle during the full power run (800 kW and 600 kW respectively). After the transition to natural circulation conditions, the power supplied to the bundle is decreased to about 30 kW simulating the decay heat. Finally the Nusselt number for the central subchannel of the fuel bundle simulator (FPS) is evaluated and compared with values obtained from Ushakov and Mikityuk correlations [6–7].

Some applications of electron beam microanalysis techniques in VLSI process evaluation

1983 ◽  
Vol 41 ◽  
pp. 160-161
Author(s):  
Simon Thomas
Keyword(s):  
Integrated Circuits ◽  
Process Evaluation ◽  
Large Scale ◽  
Technology Development ◽  
Analytical Techniques ◽  
Successful Implementation ◽  
Analysis Of Failures ◽  
Characterization Of Materials ◽  
Circuits Vlsi

Trends in the technology development of very large scale integrated circuits (VLSI) have been in the direction of higher density of components with smaller dimensions. The scaling down of device dimensions has been not only laterally but also in depth. Such efforts in miniaturization bring with them new developments in materials and processing. Successful implementation of these efforts is, to a large extent, dependent on the proper understanding of the material properties, process technologies and reliability issues, through adequate analytical studies. The analytical instrumentation technology has, fortunately, kept pace with the basic requirements of devices with lateral dimensions in the micron/ submicron range and depths of the order of nonometers. Often, newer analytical techniques have emerged or the more conventional techniques have been adapted to meet the more stringent requirements. As such, a variety of analytical techniques are available today to aid an analyst in the efforts of VLSI process evaluation. Generally such analytical efforts are divided into the characterization of materials, evaluation of processing steps and the analysis of failures.

In situ TEM studies of irradiation effects for materials improvement

1991 ◽  
Vol 49 ◽  
pp. 452-453
Author(s):  
Charles W. Allen
Keyword(s):  
Nuclear Reactor ◽  
Austenitic Stainless Steels ◽  
High Energy ◽  
Point Of View ◽  
In Situ Tem ◽  
Irradiation Effects ◽  
Tem Analysis ◽  
Radiation Induced ◽  
Analytical Tools

Irradiation effects studies employing TEMs as analytical tools have been conducted for almost as many years as materials people have done TEM, motivated largely by materials needs for nuclear reactor development. Such studies have focussed on the behavior both of nuclear fuels and of materials for other reactor components which are subjected to radiation-induced degradation. Especially in the 1950s and 60s, post-irradiation TEM analysis may have been coupled to in situ (in reactor or in pile) experiments (e.g., irradiation-induced creep experiments of austenitic stainless steels). Although necessary from a technological point of view, such experiments are difficult to instrument (measure strain dynamically, e.g.) and control (temperature, e.g.) and require months or even years to perform in a nuclear reactor or in a spallation neutron source. Consequently, methods were sought for simulation of neutroninduced radiation damage of materials, the simulations employing other forms of radiation; in the case of metals and alloys, high energy electrons and high energy ions.

Eds Of Radioactive Particles By Self-Induced Fluorescence

1990 ◽  
Vol 48 (2) ◽  
pp. 238-239
Author(s):  
Gregory L. Finch ◽  
Richard G. Cuddihy
Keyword(s):  
Electron Beam Irradiation ◽  
Nuclear Reactor ◽  
X Rays ◽  
Reactor Accident ◽  
Internal Radiation ◽  
X Ray ◽  
External Sources ◽  
X Irradiation ◽  
Available Information ◽  
Individual Particles

The elemental composition of individual particles is commonly measured by using energydispersive spectroscopic microanalysis (EDS) of samples excited with electron beam irradiation. Similarly, several investigators have characterized particles by using external monochromatic X-irradiation rather than electrons. However, there is little available information describing measurements of particulate characteristic X rays produced not from external sources of radiation, but rather from internal radiation contained within the particle itself. Here, we describe the low-energy (< 20 KeV) characteristic X-ray spectra produced by internal radiation self-excitation of two general types of particulate samples; individual radioactive particles produced during the Chernobyl nuclear reactor accident and radioactive fused aluminosilicate particles (FAP). In addition, we compare these spectra with those generated by conventional EDS.Approximately thirty radioactive particle samples from the Chernobyl accident were on a sample of wood that was near the reactor when the accident occurred. Individual particles still on the wood were microdissected from the bulk matrix after bulk autoradiography.

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