The Effect of Elevated Temperatures and Nuclear Radiation on the Properties of Biological Shielding Concrete

2016 ◽  
Vol 677 ◽  
pp. 8-16 ◽  
Author(s):  
Jaroslava Koťátková ◽  
Jan Zatloukal ◽  
Pavel Reiterman ◽  
Jan Patera ◽  
Zbyněk Hlaváč ◽  
...  
Keyword(s):  
Gamma Radiation ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Elevated Temperatures ◽  
Nuclear Radiation ◽  
Containment Vessel ◽  
Negative Impacts

The paper reviews the so far known information about the properties of biological shielding concrete used in the containment vessel of nuclear power plants (NPP) and its behaviour when exposed to radiation. The damage of concrete caused by neutron and gamma radiation as well as by the accompanying generation of heat is described. However, there is not enough data for the proper evaluation of the negative impacts and further research is needed.

scholarly journals Investigation of the characteristics of the container for storage of radioactive waste of nuclear power plants with uranium-graphite reactors

2018 ◽  
Vol 245 ◽  
pp. 07016
Author(s):  
Aleksey Ivshin ◽  
Alexandr Kalyutik ◽  
Anatolii Blagoveshchenskii
Keyword(s):  
Radioactive Waste ◽  
Gamma Radiation ◽  
Energy Range ◽  
Attenuation Coefficient ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Radiation Safety ◽  
Radiation Characteristic ◽  
Calculation Error

The article presents the results of the study of neutron-physical characteristics of the container for storage of radioactive waste of nuclear power plants with uranium-graphite reactors. The interaction of gamma quanta (in the energy range from 0.1 to 2 MeV) with the structural materials of the container is simulated. The numerical values of the parameters determining the radiation characteristic of the container with the estimation of the calculation error are obtained. The following main characteristics of the container are determined: the attenuation coefficient of the equivalent dose, the numerical factor of gamma radiation accumulation. These characteristics can be used to justify the radiation safety of the container, in particular when selecting protection materials, as well as when building additional heterogeneous protection barriers.

Finite Element Reliability Analysis of Steel Containment Vessels with Corrosion Damage

2015 ◽  
Vol 10 (3) ◽  
pp. 527-534 ◽  
Author(s):  
Xiaolei Wang ◽  
◽  
Dagang Lu ◽  
Keyword(s):  
Finite Element Analysis ◽  
Finite Element ◽  
Reliability Analysis ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Corrosion Damage ◽  
Element Analysis ◽  
Containment Vessel ◽  
Reliability Method

Containment vessels, which contain any radioactive materials that would be released from the primary system in an accident, are the last barrier between the environment and the nuclear steam supply system in nuclear power plants. Assessing the probability of failure for the containment building is essential to level 2 PSA studies of nuclear power plants. Degradation of containment vessels of some nuclear power plants has been observed in many countries, so it is important to study how the corrosion has adverse effects on the capacity of containment vessels. Conventionally, the reliability analysis of containment vessels can be conducted by using Monte Carlo Simulation (MCS) or Latin Hypercube Sampling (LHS) with the deterministic finite element analysis. In this paper, a 3D finite element model of an AP1000 steel containment vessel is constructed using the general-purpose nonlinear finite element analysis program ABAQUS. Then the finite element reliability method (FERM) based on the first order reliability method (FORM) is applied to analyze the reliability of the steel containment vessel, which is implemented by combining ABAQUS and MATLAB software platforms. The reliability and sensitivity indices of steel containment vessels under internal pressure with and without corrosion damage are obtained and compared. It is found that the FERM-based procedure is very efficient to analyze reliability and sensitivity of nuclear power plant structures.

Effects of Exposure Term on the Strength and Elasticity of Concrete Subjected to Elevated Temperature up to 175°C

2016 ◽  
Vol 711 ◽  
pp. 519-524
Author(s):  
Koichi Matsuzawa ◽  
Yoshinori Kitsutaka ◽  
Michihiko Abe ◽  
Hideo Kasami ◽  
Takafumi Tayama ◽  
...  
Keyword(s):  
Elevated Temperature ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Elevated Temperatures ◽  
Normal Weight ◽  
Normal Weight Concrete ◽  
Static Modulus ◽  
Static Modulus Of Elasticity ◽  
Concrete Component

There are many papers on the effects of high temperature on concrete, but papers about properties of concrete subjected to lower elevated temperature such used in nuclear power plants are still limited. This paper presents the results of experiments conducted to determine the effects of term of exposure to elevated temperatures below the limit for concrete component in nuclear power plants. Sealed cured cylinders made of normal weight concrete containing ordinary portland cement were subjected to temperatures from 20 to 175°C without seal for 10, 30 and 90 days. After exposure, cylinders were tested for weight loss, compressive strength and static modulus of elasticity.

Development of Rules on Concrete Containment Vessels for NPP

2016 ◽  
Author(s):  
Tomohiro Nishizawa ◽  
Takao Nishikawa ◽  
Katsuki Takiguchi ◽  
Hiroyuki Sugita ◽  
Yasuo Hijioka ◽  
...  
Keyword(s):  
Reinforced Concrete ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Containment Vessel ◽  
Safety And Reliability ◽  
Near Future ◽  
Design And Construction

“Rules on Concrete Containment Vessels for Nuclear Power Plants” was first published in 2003. It was revised in 2011 and the latest Edition was published in 2015. Endorsement of this Code is expected in the very near future. There are two types of reactor containments: steel containment vessels (hereinafter referred to as “SCV”) and concrete containment vessels (hereinafter referred to as “CCV”). The former is addressed by Rules on Design and Construction for Nuclear Power Plants, and the latter by Rules on Concrete Containment Vessels for Nuclear Power Plants, including Reinforced Concrete Containment Vessel (hereinafter referred to as “RCCV”), Pre-stressed Concrete Containment Vessel (hereinafter referred to as “PCCV”), and hybrid containment vessels which are required further safety and reliability.

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