scholarly journals STUDIES ON THERMAL DIFFUSION AND VERIFICATION OF THE THIRD NUCLEAR POWER PLANT IN TAIWAN

1986 ◽  
Vol 1 (20) ◽  
pp. 198
Author(s):  
K.C. Tang ◽  
M.T. Tsai ◽  
Y.R. Hwang ◽  
H.H. Hwung
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Numerical Simulations ◽  
Thermal Diffusion ◽  
Nuclear Power ◽  
Field Measurements ◽  
Hydraulic Model ◽  
Model Tests ◽  
The Third ◽  
Made In

In general, hydraulic model tests and numerical simulations can be used for securing enough informations in order to assess the environmental impact by thermal discharge after the power plant operation. However, the numerical simulations should be verified by the consequence of hydraulic model tests or the field data. Then, the numerical model can be used as a prediction model to foresee the nature of thermal diffusion when the additional generators will be operated. The third nuclear power plant in Taiwan has been constructed in 1984. In order to protect the abundant corals which distributed on the rocky bottom around this power plant, a complete studies on thermal diffusion have been performed, accordingly, a verification with field measurements were also made in this paper.

Chemicotechnological regime during preparation of the third block of the Leningrad Nuclear Power Plant for physical start-up

1982 ◽  
Vol 52 (2) ◽  
pp. 141-144
Author(s):  
V. M. Sedov ◽  
P. G. Krutikov ◽  
N. V. Nemirov ◽  
S. T. Zolotukhin ◽  
A. V. Devochkin ◽  
...  
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
The Third ◽  
Start Up ◽  
Leningrad Nuclear Power Plant

Application Differences of In-Service Inspection Regulations Between RSE-M2010 and ASME Section XI in China PWRs

2017 ◽  
Author(s):  
Yang Cheng ◽  
Zhang Xueliang ◽  
Xia Peng ◽  
Zeng Qingyue ◽  
Li Tian
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Technology Development ◽  
Nuclear Industry ◽  
Third Generation ◽  
Difference Analysis ◽  
The Third ◽  
Pressure Test ◽  
Service Inspection

RSE-M 2010 and ASME Section XI are the widely used and most detailed PWR in-service inspection regulations applied in China PWRs which are separately belong to French AFCEN and American ASME regulations, and come from the different nuclear industry practices of their countries. In 1987, the French M310 type reactor was imported to China and therewith the RSE-M in-service inspection regulation was introduced, beginning to be widely used in China PWRs since that time. Meanwhile, Chinese nuclear power institutes began to independently develop its own PWR reactor named Qinshan Phase I Nuclear Power Plant, and then ASME Section XI in-service inspection regulation was used which was also beginning to be widely used in some Chinese PWRs. With the nuclear power technology development and innovation, such regulations are continually updated and perfected. Thus, there are many differences during application in Chinese specific PWRs. This paper has performed quite deeply application difference analysis between the two regulations based on several aspects, such as upstream laws cited, component classification, inspection requirement, NDE, qualification, pressure test and the Safety Authority review requirements for licensing. Some preliminary thinking has been presented during applying these two regulations and some technical suggestions have been also provided to perfect the regulations in the hope to provide better reference during application on the third generation PWRs (including HPR1000) in China.

Conditioning of Radioactive Waste Resulted From the Treatment of Liquid Waste From the Romanian Nuclear Power Plant

2003 ◽  
Author(s):  
Carmen Arsene ◽  
Dumitru Negoiu
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Radioactive Waste ◽  
Nuclear Power ◽  
Liquid Waste ◽  
Organic Polymers ◽  
Research Project ◽  
Direct Immobilization ◽  
Made In

For the conditioning of spent resins contaminated with radionuclides, such as: 137Cs, 134Cs, 60Co, 58Co, 57Co, 54Mn, etc., techniques of direct immobilization in cement, bitumen and organic polymers have been tested. The selected process was the bituminization using industrial bitumen, I 60–70, made in Romania, which had very good immobilizing characteristics. The paper presents stages of the research project, technical conditions for the process and advantages of the bituminization of spent resins.

scholarly journals Lithodynamic Processes along the Seashore in the Area of Planned Nuclear Power Plant Construction: A Case Study on Lubiatowo at Poland

Energies ◽  
2021 ◽  
Vol 14 (6) ◽  
pp. 1636
Author(s):  
Piotr Szmytkiewicz ◽  
Marek Szmytkiewicz ◽  
Grzegorz Uścinowicz
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Cold Water ◽  
Water Discharge ◽  
Field Measurements ◽  
Piping System ◽  
Plant Construction ◽  
Polish Government

The Polish government has made a decision to build a nuclear power plant (NPP) in the South Baltic coastal zone. This means that three major types of structures will be located in the nearshore: (1) breakwaters and a wharf where ships may dock to load and unload cargo (harbor), (2) seawalls protecting the shore against erosion and storm surge floods, and (3) an underwater piping system for cold water intake and heated water discharge. This study determines the dominant directions and rate of sediment transport for the coastline section in the vicinity of the projected Polish NPP (ca. 100,000 m3/year), as well as assesses current changes at this coastline location on the basis of field measurements and mathematical modeling.

MEASURES AGAINST RADIOACTIVE CONTAMINATION DUE TO FUKUSHIMA FIRST NUCLEAR POWER PLANT ACCIDENTS PART I: DAMAGE SITUATION OF THE GREAT EAST JAPAN EARTHQUAKE

2012 ◽  
Vol 22 (01n02) ◽  
pp. 1-5 ◽  
Author(s):  
K. ISHII ◽  
A. TERAKAWA ◽  
S. MATSUYAMA ◽  
A. HASEGAWA ◽  
K. NAGAKUBO ◽  
...  
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
East Coast ◽  
Great East Japan Earthquake ◽  
Radioactive Pollution ◽  
Tsunami Waves ◽  
The Third ◽  
The Earth ◽  
Northeastern Japan

The great East Japan earthquake consisted of three catastrophes. The first one was the earthquake, the second one was the tsunami and the third one was nuclear power plant accidents. The magnitude 9 was recorded. After the earth quake, huge tsunami waves of above 16m height hit the east coast of Northeastern Japan. Many people died and many things were lost. The tsunami caused the accident of Fukushima first nuclear power plant which resulted in a serious radioactive pollution.

The Durability Design of the Technical Specifications for Nuclear Building Concrete of ACP1000

2017 ◽  
Author(s):  
Chen Dan ◽  
Liu Yulin ◽  
Zhang Weiguo
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Raw Materials ◽  
Site Conditions ◽  
Third Generation ◽  
The Third ◽  
Technical Requirements ◽  
Durability Design ◽  
Materials Used

For the continuous improvement of nuclear power plants safety standards, the actual requirements of the plant’s long service life, and the diversification of the plant site conditions, the durability design of nuclear building concrete structure has attracted widespread attention gradually. ACP1000, the third generation class nuclear power plant, is developed by China independently, and it may locate in different site conditions. Taking an ACP1000 nuclear power plant under construction as an example, this paper provides the technical requirements of concrete and concrete raw materials used in nuclear building. And by comparing with AP1000, the third generation class nuclear power plant imported from the United States, the advance and reasonableness of technical requirements of concrete and concrete raw materials used in nuclear building are provided further evidence.

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