Leasing of Nuclear Power Plants With Using Floating Technologies

2002 ◽  
Author(s):  
Yu. N. Kuznetsov ◽  
B. A. Gabaraev ◽  
V. A. Reshetov ◽  
V. A. Moskin
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Water Area ◽  
Industrial Association ◽  
Radioactive Materials ◽  
Power Company ◽  
Hermetic Sealing ◽  
Sea Area ◽  
The City ◽  
And Storage

The proposal to organize and realize the international program on leasing of Nuclear Power Plant (NPP) reactor compartments is brought to the notice of potential partners. The proposal is oriented to the construction of new NPPs or to replacement of worked-out reactor units of the NPPs in operation on the sites situated near water area and to the use of afloat technologies for construction, mounting and transportation of reactor units as a Reactor Compartment Block Module (RCBM). According to the offered project the RCBM is fabricated in factory conditions at the largest Russian defense shipbuilding plant — State Unitary Enterprise “Industrial Association SEVMASHPREDPRIYATIE” (SEVMASH) in the city of Severodvinsk of the Arkhangelsk region. After completion of assembling, testing and preliminary licensing the RCBM is given buoyancy by means of hermetic sealing and using pontoons and barges. The RCBM delivery to the NPP site situated near water area is performed by sea route. The RCBM is brought to the place of its installation with the use of appropriate hydraulic structures (canals, shipping locks), then is lowered on the basement constructed beforehand and incorporated into NPP scheme, of which the components are installed in advance. Floating means can be detached from the RCBM and used repeatedly for other RCBMs. Further procedure of NPP commissioning and its operation is carried out according to traditional method by power company in the framework of RCBM leasing with enlisting the services of firm-manufacturer’s specialists either to provide reactor plant operation and concomitant processes or to perform author’s supervision of operation. After completion of lifetime and reactor unloading the RCBM is dismantled with using the same afloat technology and taken away from NPP site to sea area entirely, together with its structures (reactor vessel, heat exchangers, pumps, pipelines and other equipment). Then RCBM is transported by shipping route to a firm-manufacturer, for subsequent reprocessing, utilization and storage. Nuclear fuel and radioactive wastes are removed from NPP site also. Use of leasing method removes legal problems connected with the transportation of radioactive materials through state borders as the RCBM remains a property of the state-producer at all stages of its life cycle.

A Study on the Vitrification Tests of the Low Level Radioactive Wastes Using Plasma Arc Melter System

2004 ◽  
Author(s):  
Boo Ho Yoon ◽  
Jae Hak Cho ◽  
Sang Chul Lee ◽  
Dong Woo Kang ◽  
Yong Joon Choi ◽  
...  
Keyword(s):  
Compressive Strength ◽  
Nuclear Power ◽  
Power Plants ◽  
Radioactive Wastes ◽  
Plasma Arc ◽  
Micro Hardness ◽  
Radioactive Materials ◽  
Low Level ◽  
Glass Density ◽  
Glass Formulation

For the research on the vitrification of the low-level radioactive wastes (LLRW) produced in nuclear power plants, one pilot plant with plasma arc melter system was built and several tests were done on it. Some surrogate wastes, which were spiked with several materials and were made very similar to the real LLRW, were used for these tests. For the vitrification of the surrogate wastes, the surrogate wastes were classified into the combustible, the non-combustible and the resin. Then each waste was spiked with special materials and was melted in separate. Off-gases produced in each test were picked up and analyzed. Real radioactive materials cesium (Cs) and cobalt (Co) were spiked in each wastes. Data gained from the final glass formulation were follows. Glass density is 2.42 ∼ 2.95(g/cm3), the compressive strength is 30 ∼ 175 Mpa, micro hardness is 5.5 ∼ 5.8 Gpa. The leaching ratio for Co is 1.27×10−4 ∼ 1.08×10−3 (10mL/g) and that for Cs is 2.46×10−3 ∼ 3.23×10−2 (10mL/g). The leaching speed for Co is 4.14×10−7 ∼ 5.53×10−6 (g/m2) and that for Cs is 4.58×10−5 ∼ 3.87×10−4 (g/m2). In off-gas, dioxin & furan is 0.016 mano gram on the average, CO is about 20 ppm, NO2 is about 15 ppm and SO2 is about 15 ppm.

Heat-treatment and storage technology for spent ion-exchange resins for new-generation nuclear power plants

Atomic Energy ◽  
2012 ◽  
Vol 111 (4) ◽  
pp. 276-281
Author(s):  
D. N. Babkin ◽  
N. A. Prokhorov ◽  
V. T. Sorokin ◽  
A. V. Demin ◽  
V. V. Iroshnikov
Keyword(s):  
Heat Treatment ◽  
Ion Exchange ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Ion Exchange Resins ◽  
Storage Technology ◽  
Exchange Resins ◽  
New Generation ◽  
And Storage

Relationship Between Flow Pattern and Pressure Distribution in Venturi Scrubber

2014 ◽  
Author(s):  
Naoki Horiguchi ◽  
Hiroyuki Yoshida ◽  
Akiko Kaneko ◽  
Yutaka Abe
Keyword(s):  
Flow Rate ◽  
Nuclear Power ◽  
Power Plants ◽  
Gas Flow ◽  
The Self ◽  
Radioactive Materials ◽  
Venturi Scrubber ◽  
Nuclear Disaster ◽  
Severe Accidents ◽  
Main Components

As revealed by Fukushima Daiichi nuclear disaster, countermeasures against severe accidents in nuclear power plants are an urgent need. In particular, from the viewpoint of protecting containment and suppressing diffusion of the radioactive materials, it is most important to install filtered venting devices to release high pressure contaminated gas to the atmosphere with elimination radioactive materials in the gas. A Multi Venturi Scrubber System (MVSS) is one of the filtered venting devices, and used in European reactors [1, 2]. One of the main components of the MVSS is a Venturi Scrubber (VS). It is considered that a dispersed or dispersed annular flow is formed in the VS by a self-priming phenomena. In the self-priming phenomena, the liquid was suctioned from a surrounding region of the VS to the inside of the VS. And a part of the radioactive materials are eliminated through the gas-liquid interface of the dispersed or annular dispersed flow. Therefore, to consider the MVSS operation characteristics, it is important whether to occur the self-priming or not and the liquid flow rate of the self-priming of the VS. The objective of this paper is to understand the self-priming phenomena of the VS for the filtered venting. And theoretical analysis and experiment were conducted. By comparing these results, we discussed about the mechanism of the self-priming phenomena. As results, the self-priming phenomena in the VS was confirmed and, at a high gas flow rate, the suspension of the self-priming is confirmed experimentally and theoretically.

scholarly journals Hydrometeorological monitoring in the Nizhny Novgorod NPP siting area

2021 ◽  
Vol 263 ◽  
pp. 05012
Author(s):  
Fedor Bryukhan ◽  
Aleksey Vinogradov ◽  
Ivan Vinogradov
Keyword(s):  
Surface Waters ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Climate Changes ◽  
Environmental Safety ◽  
Data Series ◽  
Observation Data ◽  
Industrial Association ◽  
Construction Operation

Ensuring the technological and environmental safety of nuclear power plants (NPP) involves the collection and analysis of data on the state of the natural environment near nuclear power plants, including the atmosphere and surface waters. To obtain and organize such data, as well as for their subsequent processing and engineering calculations, appropriate monitoring observations are provided. The latter begin to be carried out long before the start of NPP construction and continue at all stages of the NPP life cycle, including the periods of construction, operation and decommissioning of the plant. The purpose of this research is to summarize the results of hydrometeorological monitoring at the Nizhny Novgorod NPP site and its vicinity, which was launched by the Scientific & Industrial Association Gidrotekhproekt in 2011. The description of stationary observation points and examples of calculation of regime hydrological and meteorological characteristics are given. It is noted that the accumulation of observation data series over a long period of time, which make it possible to identify potential climate changes in the study area, is of great importance.

scholarly journals Criminal Liability for Illicit Trafficking of Radioactive Materials

2018 ◽  
pp. 66-70
Author(s):  
O. V. Taran ◽  
O. G. Sandul
Keyword(s):  
Social Relations ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Energy ◽  
Energy Use ◽  
Radiation Safety ◽  
Criminal Liability ◽  
Criminal Code ◽  
Radioactive Material ◽  
Radioactive Materials

The nuclear energy use progressively becomes part of the life of every modern person, who more and more faces radioactive materials in medical institutions, in industry. Half of all electricity generated in Ukraine is generated by nuclear power plants. The peculiarities of the nuclear energy use generate appropriate rules for people dealing with radioactive materials. The article analyzes the standards of the Criminal Code of Ukraine, which provides for liability for acts related to the illegal handling of radioactive materials, for violation of the nuclear and radiation safety rules, violation of radiation safety requirements, the threat of theft of radioactive materials, the illicit manufacturing of a nuclear explosive device, abduction or capture of radioactive materials, attack on radioactive materials transportation means. The grounds and peculiarities for bringing to criminal liability have been reviewed, the range of persons who can be prosecuted has been defined. Conditions and grounds for exemption from criminal liability in the absence of a person's criminal intent to use radioactive material are considered. It has been demonstrated that the Criminal Code of Ukraine, by prohibiting certain actions on the illegal radioactive materials handling, ensures protection of the most important social relations and social benefits.

Management of Radioactive Waste and Materials Arising From the Decommissioning of Italian Nuclear Power Plants

2001 ◽  
Author(s):  
Gaetano Ruggeri ◽  
Luigi Brusa
Keyword(s):  
Radioactive Waste ◽  
Boundary Conditions ◽  
Electricity Market ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Local Level ◽  
Global Strategy ◽  
Acceptance Criteria ◽  
Radioactive Materials

Abstract Scope of the paper is to summarise the experience about management of materials arising from decommissioning of Italian NPPs, and to illustrate criteria, procedures and systems, which Sogin is defining to manage the problem of the clearance of sites and materials, considering the international experience and boundary conditions existing in the Country. Since 1962 Enel (the largest Italian utility for electric power) has operated the four Italian nuclear power plants: Garigliano (160 MWe BWR), Latina (210 MWe GCR), Trino (270 MWe PWR) and Caorso (882 MWe BWR). These NPPs were shutdown in the 80’s: Garigliano NPP was shutdown in 1982 following a decision made by Enel, based on technical and economical reasons, Latina, Trino and Caorso NPPs following decisions made by the Italian Government after the Chernobyl accident. The “deferred decommissioning (SAFSTOR)” was the decommissioning strategy selected by Enel and approved by the competent Authorities, due to the lack of a repository for the disposal of radioactive materials and of release limits for clearance of materials. Activities have been started aimed at reaching the “Safe Enclosure” condition, which would have lasted for some decades, before final dismantling of plants. In 1999 the liberalisation of the Italian electricity market led Enel to separate its nuclear activities, forming a new Company, named Sogin, to which decommissioning Italian NPPs was committed. At the same time, considering pressures, both at national and local level, to adopt the “prompt decommissioning (DECON)” strategy, in December 1999 the Italian Minister of Industry, with the intent to accelerate the dismantling of Italian NPPs, presented the plans to create a national repository for nuclear waste, and asked Sogin to revise the decommissioning plans, according to the new global strategy, taking into account all the relevant technical, organisational, financial and legislative aspects of the problem. As the DECON strategy enhances the importance of “clean-up” both of sites and materials, the related aspects are held in due consideration in developing the decommissioning plans, which deal with the following: • characterisation of plant systems, components and structures; • decontamination and dismantling techniques; • monitoring of dismantled materials for clearance; • treatment of dismantled, radioactive materials (which cannot be cleared), prior to disposal; • treatment and conditioning of radioactive waste, prior to disposal; • final clearance of sites. Authorisation requirement related to the release, recycle and reuse of materials produced during plant decommissioning, together with the acceptance criteria for disposal of radioactive materials, are of key importance, considering that the change in decommissioning strategy increases the quantity of radioactive waste to be disposed of, the costs for waste treatment, transportation and disposal, and the capacity of the national repository. In this connection, Sogin is discussing with competent Authorities and Bodies in order to define clearance criteria and disposal acceptance criteria, which neither impair nor complicate the future dismantling operations. In (1) details are given about Italian decommissioning Regulation, decommissioning strategy and Organisation, in order to show the boundary conditions, which exist in Italy for planning and development of NPPs Decommissioning Projects. In the following paragraphs the decommissioning strategy is summarised first together with some critical items of decommissioning; then the Italian regulation about the management of radioactive waste is reported. The management of waste and materials, which will arise from the decommissioning of Italian nuclear power plants, is driven by the requirements imposed by the competent Authorities basing on this regulation.

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