Material Selection Methodology Used in Czech NPP

2011 ◽  
Vol 133 (1) ◽  
Author(s):  
Karel Matocha
Keyword(s):  
Czech Republic ◽  
Material Properties ◽  
Nuclear Power ◽  
Power Plants ◽  
Mechanical Characteristics ◽  
Material Selection ◽  
Technical Documentation ◽  
Parent Materials ◽  
Materials Used ◽  
Selection Methodology

This paper describes the structure of the Standard Technical Documentation of the Association of Mechanical Engineers of Czech Republic, Sec. II, “Material Properties for Equipments and Pipings of Water moderated, Water Cooled Energy Reactor (WWER) Nuclear Power Plants (NPPs).” It provides instructions for selection and qualification of parent materials used for manufacture, repair, reconstruction, or replacement of selected equipments of WWER NPP, and specifies requirements for mechanical characteristics and physical properties.

Material Selection Methodology Used in Czech NPP

2009 ◽  
Author(s):  
Karel Matocha
Keyword(s):  
Physical Properties ◽  
Material Properties ◽  
Nuclear Power ◽  
Power Plants ◽  
Mechanical Characteristics ◽  
Material Selection ◽  
Technical Documentation ◽  
Parent Materials ◽  
Materials Used ◽  
Selection Methodology

The paper describes the structure of the Standard Technical Documentation A.M.E Section II “Material Properties for Equipments and Pipings of WWER Nuclear Power Plants”. It provides instructions for selection and qualification of parent materials used for manufacture, repair, reconstruction or replacement of selected equipments of WWER NPP and specifies requirements for mechanical characteristics and physical properties.

Research Progress on Radiation Shielding Concrete

2012 ◽  
Vol 253-255 ◽  
pp. 303-307 ◽  
Author(s):  
Jing Yang ◽  
Zhen Fu Chen ◽  
Yuan Chu Gan ◽  
Qiu Wang Tao
Keyword(s):  
Nuclear Waste ◽  
Material Properties ◽  
Nuclear Power ◽  
Power Plants ◽  
Radiation Shielding ◽  
Nuclear Industry ◽  
Research Progress ◽  
Concrete Durability ◽  
Technology Research ◽  
Shielding Material

Radiation shielding concrete is widely used in nuclear power plants, accelerators, hospitals, etc. With the development of nuclear industry technology, research on radiation shielding material properties is of great importance. Research on properties of radiation shielding concrete with different aggregates or admixtures and the effect of high temperature on the performance of shielding concrete are introduced. Along with the nuclear waste increase, shielding concrete durability and nuclear waste disposal are getting paramount.

Development of Concretes with Resistance to High Temperatures in the Czech Republic and Surrounding European Countries

2013 ◽  
Vol 651 ◽  
pp. 120-125 ◽  
Author(s):  
Lenka Bodnárová ◽  
Jiri Zach ◽  
Jitka Hroudová ◽  
Jaroslav Válek
Keyword(s):  
Czech Republic ◽  
High Temperatures ◽  
Nuclear Power ◽  
Power Plants ◽  
Building Materials ◽  
European Countries ◽  
Terrorist Attacks ◽  
Load Bearing Capacity ◽  
The Czech Republic ◽  
The Stability

The resistance of concrete constructions to high temperatures at present is a much monitored issue for many scientific teams and experts in the stated area. This fact is mainly caused by fatal consequences originating in the case when concrete constructions are loaded by the effect of fire and consequent loss of their load-bearing capacity, for the population and the environment of our planet, in which we live in. The development of society goes hand in hand with the development of new building materials and as a consequence the requirements for building constructions increase which bring about extraordinary strict regulations in the area of fire safety. So, many high, non-traditional or specific constructions originate, e.g. nuclear power plants due to permanently higher demand for transport linkage and many tunnels have originated between European countries as a result. Unfortunately, in this relation the threat of terrorist attacks increases and unexpected natural disasters which also threaten the stability of the mentioned constructions. The objective of the article is to familiarize readers with the results of research concerning the improvement of the resistance of the concrete to high temperatures originated during fire instances.

Research on the Micro-Mechanical State at Tip of Environmentally Assisted Cracking Based on Latin Hypercube Sampling Method

2019 ◽  
Vol 795 ◽  
pp. 74-78
Author(s):  
Kuan Zhao ◽  
He Xue ◽  
Ling Yan Zhao
Keyword(s):  
Oxide Film ◽  
Material Properties ◽  
Nuclear Power ◽  
Power Plants ◽  
Sampling Method ◽  
Latin Hypercube Sampling ◽  
Primary Circuit ◽  
Mechanical State ◽  
Latin Hypercube ◽  
Environmentally Assisted Cracking

Environmentally assisted cracking (EAC) of nickel-based alloys is one of the most significant potential safety hazards in the primary circuit of nuclear power plants. To understand the influence of randomness on micro-mechanical state at tip of EAC, Latin hypercube sampling method is applied to analyze the uncertainty of stress-strain in the oxide film at the EAC tip considering the uncertainties of load and material properties of base metal and oxide film. Meanwhile, to improve the efficiency of numerical analysis, MATLAB is employed in the secondary development for ABAQUS. With the help of finite element numerical simulation and Latin hypercube sampling method, the uncertainty of mechanical properties at tip of EAC in one-inch compact tension specimen is simulated and analyzed in this study. The results show that the randomness of material properties and load markedly affect the uncertainty of micro-mechanical state. Among the variables, The randomness of load has the greatest influence on uncertainty of strain, and Poisson`s ratio of oxide film is the smallest effect.

scholarly journals Feasibility of replacement of nuclear power with other energy sources in the Czech republic

2020 ◽  
Vol 24 (6 Part A) ◽  
pp. 3543-3553
Author(s):  
Pavel Charvat ◽  
Lubomir Klimes ◽  
Jiri Pospisil ◽  
Jiri Klemes ◽  
Petar Varbanov
Keyword(s):  
Czech Republic ◽  
Natural Gas ◽  
Nuclear Power ◽  
Power Plants ◽  
Fossil Fuels ◽  
Renewable Energy Sources ◽  
Combined Cycle ◽  
Energy Sources ◽  
The Czech Republic ◽  
The Moment

The feasibility and consequences of replacing nuclear power plants (NPP) in the Czech Republic with other energy sources are discussed. The NPP produced about one-third of electricity in the Czech Republic in 2017. Renewable energy sources such as hydropower, wind and solar power plants and biomass/biogas burning power plants produced about 11% of electricity in 2017. Due to the geographical and other constraints (intermittency, land footprint, and public acceptance), the renewables do not have the potential to entirely replace the capacity of the NPP. The only feasible technologies that could replace NPP in the Czech Republic in the near future are the power plants using fossil fuels. The combined cycle power plants running on natural gas (NGCC) are technically and environmentally fea-sible alternative for NPP at the moment. However, the natural gas imports would increase by two-thirds and the total greenhouse gas emissions would go up by about 10% if the power production of the NPP was entirely replaced by NGCC in the Czech Republic.

Neutronic Analysis for VVER-440 Type Reactor Using PARCS Code

2018 ◽  
Author(s):  
Luca Ratti ◽  
Guido Mazzini ◽  
Marek Ruščák ◽  
Valerio Giusti
Keyword(s):  
Czech Republic ◽  
Cross Sections ◽  
Nuclear Power ◽  
Power Plants ◽  
Computational Models ◽  
Reactor Core ◽  
Sensitivity Study ◽  
The Czech Republic ◽  
State Office ◽  
Scale Models

The Czech Republic National Radiation Protection Institute (SURO) provides technical support to the Czech Republic State Office for Nuclear Safety, providing safety analysis and reviewing of the technical documentations for Nuclear Power Plants (NPPs). For this reason, several computational models created in SURO were prepared using different codes as tools to simulate and investigate the design base and beyond design base accidents scenarios. This paper focuses on the creation of SCALE and PARCS neutronic models for a proper analysis of the VVER-440 reactor analysis. In particular, SCALE models of the VVER-440 fuel assemblies have been created in order to produce collapsed and homogenized cross sections necessary for the study with PARCS of the whole VVER-440 reactor core. The sensitivity study of the suitable energy threshold to be adopted for the preparation with SCALE of collapsed two energy-group homogenized cross sections is also discussed. Finally, the results obtained with PARCS core model are compared with those reported in the VVER-440 Final Safety Report.

History of A.M.E. Standard Creation

2009 ◽  
Author(s):  
Stanislav Vejvoda
Keyword(s):  
Czech Republic ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Technical Documentation ◽  
The Czech Republic ◽  
Special Cases ◽  
History Of ◽  
Plant Components

Czechoslovak specialists participated in creation of the Interatomenergo standards for design of WWER type nuclear power plant components from 1980 to 1989. The Interatomenergo standards had not been accepted as official standards in the Czech Republic. Temelin power plant was built in the ninetieth years of last century, but any public requirement followed the existing creation of the national nuclear standards of that time. The Standard Technical Documentation (STD) was asked for assessment of strength and lifetime analyses of components manufactured for the Temelin nuclear power plant. The Association of Mechanical Engineers (A.M.E) issued six Sections and one Section of Special Cases of the Standard Technical Documentation. Revisions of these Sections are made every three years with last revision being published in 2007.

Decommissioning of Obsolete Nuclear Facilities in the Nuclear Research Institute Rez

2011 ◽  
Author(s):  
Josef Podlaha ◽  
Karel Svoboda ◽  
Eduard Hansli´k
Keyword(s):  
Czech Republic ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Research ◽  
Current Status ◽  
Joint Stock Company ◽  
Nuclear Facilities ◽  
Nuclear Research Institute ◽  
The Czech Republic ◽  
Research Institute

After more than 55 years of activities of the Nuclear Research Institute Rez (NRI) in the nuclear field, there are some obsolete nuclear facilities that shall be decommissioned. NRI is a leading institution in all areas of nuclear R&D in the Czech Republic. NRI has had a dominant position in the nuclear programme since it was established in 1955 as a state-owned research organization and it has developed to its current status. In December 1992, NRI has been transformed into a joint-stock company. The Institute’s activity encompasses nuclear physics, chemistry, nuclear power, experiments at the research reactor and many other topics. Main issues addressed in NRI in the past decades were concentrated on research, development and services provided to the nuclear power plants operating VVER reactors, development of chemical technologies for fuel cycle and irradiation services to research and development in the industrial sector, agriculture, food processing and medicine. The NRI operates two research nuclear reactors, many facilities as a hot cell facility, research laboratories, technology for radioactive waste (RAW) management, radionuclide irradiators, an electron accelerator, etc. The obsolete facilities to be decommissioned comprise various research facilities and facilities for RAW management. Decommissioning of nuclear facilities NRI is the only ongoing decommissioning project in the Czech Republic. Decommissioning started in 2003 and will be finished in 2014. Some facilities have already been successfully decommissioned.

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