Reinforced Concrete Design for Thermal Effects on Nuclear Power Plant Structures

10.14359/7017 ◽  
1980 ◽  
Vol 77 (6) ◽  
Keyword(s):  
Reinforced Concrete ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Thermal Effects ◽  
Nuclear Power

scholarly journals Thermal effects on heterotrophic processes in a coastal ecosystem adjacent to a nuclear power plant

2006 ◽  
Vol 309 ◽  
pp. 55-65 ◽  
Author(s):  
FK Shiah ◽  
TH Wu ◽  
KY Li ◽  
SJ Kao ◽  
YF Tseng ◽  
...  
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Thermal Effects ◽  
Nuclear Power ◽  
Coastal Ecosystem

scholarly journals HYDROTHERMAL MONITORING: SURRY NUCLEAR POWER PLANT

1974 ◽  
Vol 1 (14) ◽  
pp. 143
Author(s):  
C.S. Fang ◽  
G. Parker ◽  
W. Harrison
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Thermal Effects ◽  
Nuclear Power ◽  
Monitoring Program ◽  
First Year ◽  
James River ◽  
Background Data ◽  
Monitoring Effort ◽  
One Year

A hydrothermal monitoring program has been designed and deployed to gather data on the temperature distribution in the tidal James River near the outfall of the Surry Nuclear Power Plant at Surry, Virginia, U.S.A. Monitoring to date has included two years of background data (1971 and 1972) taken prior to plant operation, and one year (19 73) of data with the plant in operation. The results of the first year post operational monitoring effort has been compared with the pre-operation background data and with the thermal effects that were predicted from studies by Carpenter and Pritchard on the James River Hydraulic Model at Vicksburg, Mississippi.

Assessment of Aging of Nuclear Power Plant Civil Structures

2002 ◽  
Author(s):  
D. J. Naus ◽  
B. R. Ellingwood ◽  
H. L. Graves
Keyword(s):  
Reinforced Concrete ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Structural Reliability ◽  
Operating Experience ◽  
Assessment Tools ◽  
Background Information ◽  
Civil Structures ◽  
Age Related

Research is being conducted by ORNL for the USNRC to address aging of civil structures in light-water reactor plants. The importance and operating experience of nuclear power plant (NPP) civil structures is reviewed. Factors that can lead to age-related degradation of reinforced concrete structures and containment metallic pressure boundaries (i.e., steel containments and liners of reinforced concrete containments) are identified and their manifestations described. Background information and data for improving and developing methods to assess the effects of age-related degradation on structural performance are provided. Techniques for detection of degradation are reviewed and research related to development of methods for inspection of inaccessible regions of the containment pressure boundary presented. Application of structural reliability analysis methods to develop condition assessment tools and guidelines is described.

Behavior of Reinforced Concrete Subjected to Boric Acid Corrosion of Nuclear Power Plant

2011 ◽  
Vol 250-253 ◽  
pp. 242-246 ◽  
Author(s):  
Yuan Zhan ◽  
Qiang Li ◽  
Xian Yu Jin ◽  
Ye Tian ◽  
Nan Guo Jin
Keyword(s):  
Reinforced Concrete ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Bond Strength ◽  
Boric Acid ◽  
Nuclear Power ◽  
Acid Corrosion ◽  
Mass Loss Rate ◽  
Steel Bar ◽  
Flexural Bearing Capacity

Reaches on durability of concrete has been made great advances over the past decades. However, little works have been done on the corrosion of reinforced concrete exposed to boric acid in cooling pond of heating exchange system of nuclear power plant. The purpose of this study is to experimentally investigate the behavior of reinforced concrete in such circumstance. Tests were carried out on specimens cured in a standard moisture room at a temperature of 20±3°C. Three different concentration of boric solution (2000ppm, 8000ppm, 30000ppm) were simulated to accelerate the corrosion. The compressive and splitting tensile strength,elastic modulus of concrete , mass loss rate of steel bar, bond strength and flexural bearing capacity of reinforced concrete at 60, 90, 120, 150 and 180 days were obtained respectively. The results indicate that the presence of boric acid below 30000ppm does not significantly affect serviceability of concrete. The corrosion is slight for the specimens with crack less than 0.4 mm under flexural loads. Boric acid almost has no effect on the corrosion of the steel bar and bond strength.

scholarly journals Proposal of Laser-Induced Ultrasonic Guided Wave for Corrosion Detection of Reinforced Concrete Structures in Fukushima Daiichi Nuclear Power Plant Decommissioning Site

2019 ◽  
Vol 9 (17) ◽  
pp. 3544 ◽  
Author(s):  
Akinori Furusawa ◽  
Yusuke Takenaka ◽  
Akihiko Nishimura
Keyword(s):  
Reinforced Concrete ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Wavelet Transforms ◽  
Nuclear Power ◽  
Concrete Structures ◽  
Guided Wave ◽  
Reinforced Concrete Structures ◽  
Ultrasonic Guided Wave ◽  
Fukushima Daiichi

Remote-controlled, non-destructive testing is necessary to detect corrosion of the reinforced concrete structures at the Fukushima Daiichi Nuclear Power Plant (NPP) de-commissioning site. This work aims to demonstrate that laser-induced ultrasonic guided wave technology can be applied to achieve this task. Hence, accelerated electrolytic corrosion is performed on a reinforced concrete specimen fabricated by embedding a steel rod into mortar. Waveforms of the laser-induced ultrasonic guided wave on the rod are measured with a previously employed piezoelectric transducer (PZT) probe, for each fixed corrosion time. Based on the results of Fourier and wavelet transforms of the waveforms, issues concerning the detection and extent of rebar corrosion are discussed. It is exhibited that the changes in bonding strength due to corrosion are distinguishable in the frequency domain of the ultrasonic signal.

Load Combination Reduction Methodology for the US EPR™ Standard Nuclear Power Plant

2012 ◽  
Author(s):  
Se-Kwon Jung ◽  
Joseph Harrold ◽  
Nawar Alchaar
Keyword(s):  
Reinforced Concrete ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Reduction Process ◽  
Shear Walls ◽  
Related Structure ◽  
Design Component ◽  
Load Combination ◽  
The U.S

The Safety-Related structures of the U.S. EPR™ Standard Nuclear Power Plant (NPP) predominantly consist of reinforced concrete shear walls and slabs; thus they are typically modeled using shell finite elements and analyzed and designed for a large number of applicable load combinations. This paper presents a load combination reduction methodology that has been specifically developed for and applied to these types of structural elements in order to methodically reduce the full set of applicable load combinations to a manageable sub-set of load combinations, termed “controlling load combinations” for structural design purposes. Load combination reduction criteria involve code-specified section capacities (i.e., allowables), structural demands (i.e., forces and moments), and demand-to-capacity ratios (DCR) as complemented by reinforcing ratios. For a particular Safety-Related structure or portions thereof, the controlling load combination produces the most demanding forces and moments relative to design allowables in accordance with applicable codes and standards for reinforced concrete design, resulting in the highest DCR among all applicable load combinations. To facilitate the load combination reduction process, portions or segments of a particular Safety-Related structure that are in close proximity and thereby most likely to be designed for a common reinforcement pattern are identified and grouped as a single design component and termed an “evaluation level component.” It is demonstrated that the load combination reduction methodology developed herein is instrumental in narrowing down numerous applicable load combinations to a sub-set of controlling load combinations for the U.S. EPR™ Nuclear Island Safety-Related structures.

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