Corrosion at Nuclear Power Plant from Mössbauer Spectroscopy Point of View

2010 ◽  
Author(s):  
V. Slugeň ◽  
J. Lipka ◽  
J. Dekan ◽  
I. Tóth ◽  
I. Smieško ◽  
...  
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Point Of View

Equipment Aging Management and Operational Lifetime Extension at the PAKS Nuclear Power Plant

2004 ◽  
Author(s):  
T. Katona ◽  
A. Ja´nosine´ Bi´ro´ ◽  
S. Ra´tkai ◽  
T. Pa´lfi ◽  
A. To´th
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Point Of View ◽  
Operational Lifetime ◽  
Periodic Safety ◽  
Main Components ◽  
License Renewal ◽  
Ageing Management ◽  
Lifetime Extension

The design life of the NPP PAKS VVER-440/213 Units is 30 years. The Paks Nuclear Power Plant strategy is to extend the operational lifetime of the plant and renew the operational license for 20 years over the designed and licensed lifetime. The feasibility of plant lifetime extension has been investigated. It has been found that a 20 years extension of operation is feasible from both technical and business point of view. The Licence Renewal regulation based mainly on USNRC approach taking into account the special features of the VVER-440/213 Units and the Periodic Safety Review (PSR) (every 10 years) requirements based on IAEA methods. At Paks NPP the systematic ageing management activities were started ten years ago. Basic results of plant assessment and aging management programs of the main components are discussed in the paper. Summary of the license renewal process and details of the main activities are reported.

scholarly journals Analysis of the possibility for operating a floating nuclear power plant in conjunction with a desalination plantAnalysis of the possibility for operating a floating nuclear power plant in conjunction with a desalination plant

2021 ◽  
Vol 2 (396) ◽  
pp. 149-158
Author(s):  
I. Chesnokova ◽  
◽  
S. Verbitsky ◽  
E. Stambrovskaya ◽  
◽  
...  
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Power Unit ◽  
Nuclear Power ◽  
Optimal Choice ◽  
Point Of View ◽  
Thermal Methods ◽  
Desalination Plant ◽  
Nuclear Power Unit ◽  
The Persian Gulf

Object and purpose of research. The article discusses in comparison the methods of desalination of seawater and their energy features from the point of view of the feasibility of including a desalination plant in the complex with a floating nuclear power unit. Materials and methods. Based on the analysis of various literary sources, a review of the main methods of nuclear desalination is made. The IAEA DEEP program was used to compare different desalination technologies. Main results. Based on the results of simulating nuclear desalination in the IAEA DEEP program, using the example of the Persian Gulf, preliminary recommendations were drawn up on the use of desalination methods in the joint operation of a desalination plant with a floating nuclear power unit. Conclusion. The integrated complex allows for desalination by both membrane and thermal methods. For the optimal choice of technology, it is necessary to specify the area of deployment and the relative position of the floating nuclear power unit and the desalination plant, and further search for a compromise based on more accurate calculations.

Transport of the Reactor Pressure Vessels in the Greifswald Nuclear Power Plant

2009 ◽  
Author(s):  
Ralf Borchardt
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Operation Time ◽  
Pressure Vessels ◽  
Point Of View ◽  
New Strategy ◽  
Interim Storage ◽  
Reactor Pressure ◽  
Reactor Internals

Five WWER-440 reactors are being dismantled on the Greifswald Nuclear Power Plant (KGR) site. The strategy for the dismantling of the reactor units 1 to 4 (operation time 12–17 years) was to cut and pack the components remotely. For this purpose dry and wet cutting areas were installed. The remote cutting and packing of the reactor pressure vessel and its internals was successfully tested with non-activated original reactor components of units 7 and 8 from October 1999 until July 2003. From August 2004 until July 2007 the internals from reactor units 1 and 2 were cut, packed and transported to the on-site Interim Store North (ISN). For the reactor 5 it was planned to transport the RPV in one piece and the reactor internals in shielding and transport containers to the interim store for decay storage. In December 2003 the RPV of unit 5 was lifted and transported to the interim store. From April 2006 up to July 2006 the reactor internals of unit 5 were packed and transported to the interim store. After the evaluation of the experience made during the transport and the radiological measurements and samplings taken from the RPV unit 1, the strategy for the dismantling of the reactors was changed. The reactor pressure vessels of the units 1 to 4 and the reactor internals of the units 3 and 4 should be removed as complete parts and stored as shielded large components in the ISN. In summer 2005 EWN applied for the new strategy at the responsible licensing authority and in August 2007 this license was granted. In November 2007 the reactor pressure vessels of the units 1 and 2 were transported into the ISN. The transport of the reactor pressure vessels and the internals from units 3 and 4 is planned in the period from March till September 2009. These transports of the reactor pressure vessels and internals show that the dismantling of the reactors with dismantling and interim storage of large components could not only be an alternative for cutting but could also be favored from the economical and radiological point of view.

Life Extension of Bolted Flanged Connections From a Design Peculiarities Point of View

2004 ◽  
Author(s):  
Anatoly I. Efremov
Keyword(s):  
Experimental Data ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Point Of View ◽  
Life Extension ◽  
Design Improvement ◽  
Power Plant Equipment ◽  
Bolt Preload ◽  
Plant Equipment

Life extension of Bolted Flanged Connections (BFC) depends directly on early leakage that is a major cause of bolt degradation and failure. Experiments with standard BFC typically used in Nuclear Power Plant equipment and subjected to bolt preload and subsequent internal pressure revealed an influence of the BFC design peculiarities on early leakage. The experimental data became a basis for BFC design improvement.

Review of the Primary and Secondary Water Chemistry Operation of Paks Nuclear Power Plant From the Point of View of Lifetime Extension

2008 ◽  
Author(s):  
A´rpa´d Doma
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Water Regime ◽  
Life Time ◽  
Point Of View ◽  
Expert Review ◽  
Huge Data ◽  
Time Extension ◽  
Lifetime Extension

The review of the water regime used for the Units of Paks Nuclear Power Plant was carried out in 2005, after 18 – 23 years of operation. It was clearly concluded after processing the huge data base of the water regime, that there is nothing to prevent the life time extension of the Units. In 2006, a new water regime was developed that will be applied during the preparation for the life time extension and the extended service life as well. In connection with this work, recommendations were made for some modifications of the previously used water regime. Currently there is no uniform startup and shutdown water regime for WWER-440 Units. Therefore, special attention was paid to developing of a startup water regime, which will be applied for the outages as early as 2008. The summarised recommendations for water regime modification will be subject to international expert review in 2008, and the modifications judged to be implemented will be finalised after the review.

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