Rate constant for the H˙ + H2O → ˙OH + H2 reaction at elevated temperatures measured by pulse radiolysis

2017 ◽  
Vol 19 (45) ◽  
pp. 30834-30841 ◽  
Author(s):  
Y. Muroya ◽  
S. Yamashita ◽  
P. Lertnaisat ◽  
S. Sanguanmith ◽  
J. Meesungnoen ◽  
...  

Maintaining the structural integrity of materials in nuclear power plants is an essential issue associated with safe operation.

Author(s):  
Myung-Hwan Boo ◽  
Kyoung Soo Lee ◽  
Hyun-Su Kim ◽  
Chang-Kyun Oh

In accordance with the recommendation of USNRC and the U.S. license renewal experiences, the effect of reactor coolant environment on the fatigue life has to be considered for the continued operation of operating nuclear power plants as well as for the design of new plants in Korea. The reason is that it is very important to maintain the structural integrity and reliability of the nuclear power plants against the fatigue failure during operation. Fatigue monitoring system has been considered as a practical way to ensure safe operation of the nuclear power plants in terms of the fatigue. The fatigue monitoring system evaluates various plant conditions and their effects on the monitored location to give quantified value that indicates accumulated fatigue damage up to date. From this, the authors have developed a fatigue monitoring system, named NuFMS (Nuclear Fatigue Monitoring System) in web environment and has been being applied widely to Korean nuclear plants. In this paper, overall configuration and characteristics of the NuFMS are described in detail.


2005 ◽  
Vol 19 (11) ◽  
pp. 1988-1997 ◽  
Author(s):  
June-soo Park ◽  
Ha-cheol Song ◽  
Ki-seok Yoon ◽  
Taek-sang Choi ◽  
Jai-hak Park

Author(s):  
Holger Schmidt ◽  
Martin Betz ◽  
Ingo Ganzmann ◽  
Achim Beisiegel ◽  
Thomas Wagner ◽  
...  

Atomic Energy ◽  
2006 ◽  
Vol 101 (2) ◽  
pp. 539-543 ◽  
Author(s):  
Yu. G. Dragunov ◽  
V. P. Denisov

Author(s):  
R. S. Soni ◽  
R. K. Mishra ◽  
M. K. Agrawal ◽  
G. R. Reddy ◽  
H. S. Kushwaha ◽  
...  

In nuclear power plants, it is essential to design the various safety and safety related systems and components of the plant in such a manner that they maintain their structural integrity as well as serve their functional performance during a seismic event. The pre-operational seismic walk-through helps in ensuring the installation of various seismic supports as per design intent, identifying the areas where supports are inadequate, identifying the interaction concerns between the systems of various safety classes and locating the various undesired loose, untied / unanchored components, tools, etc. used during the construction activity. A detailed procedure for the pre-operational seismic walk-through of the NPPs was therefore, prepared. Since the types and locations of seismic supports for the various systems and components of the plant had been already reviewed, the major emphasis during the walk-through was laid on their proper installation.


2016 ◽  
Vol 677 ◽  
pp. 8-16 ◽  
Author(s):  
Jaroslava Koťátková ◽  
Jan Zatloukal ◽  
Pavel Reiterman ◽  
Jan Patera ◽  
Zbyněk Hlaváč ◽  
...  

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.


Author(s):  
Fumio Inada ◽  
Tomomichi Nakamura ◽  
Takashi Nishihara ◽  
Shigehiko Kaneko ◽  
Manwoong Kim ◽  
...  

In nuclear power plants, fluid structure interactions (FSI) occurring in component systems can cause excessive forces or stresses to the structures resulting in mechanical damages that may eventually threaten the structural integrity. FSI in the guidelines includes flow-induced vibration, water hammer, and pipewhip. It can also include movement, deformation, or fracture of equipments by tsunami etc. They can be issues of design and maintenance. Authors cannot find complete guidelines to correspond to the FSI phenomena which can be important in the design and maintenance of nuclear power plants. Based on the background, International Atomic Energy Agency (IAEA) has drafted guidelines on FSI. This paper summarizes general description of FSI as well as design and maintenance against FSI.


Author(s):  
Balhassn S. M. Ali

Most of the large components in the thermal, traditional and nuclear power plants such as pressurized vessels and pipes are operating at elevated temperatures. These temperatures and stress are high enough for creep to occur. For variety of reasons many of these power plants are now operating beyond their design life time. It is -known fact that as the high temperature components aged the failure rate normally increases as a result of their time dependent material damage. Further running of these components may become un-safe and dangerous in some cases. Therefore, creep assessment of the high temperature components of these plants is essential for their safe operation. Mainly for economic reasons these components have to be creep assessed as they are in service. However, assessing the creep strength for these high temperature components as they are in service, it can be challenging task, especially when these components are operating under extremely high temperature and/or stress. This paper introduces newly invented, small creep test specimens techniques. These new small types of specimens can be used to assess the remaining life times for the high temperature components, using only small material samples. These small material samples can be removed from the operating components surface, without affecting their safe operation. Two of the high temperature materials are used to validate the new testing techniques.


2021 ◽  
Author(s):  
Sam Sadeghi

Safety is the most important aspect and is considered the overwriting priority in nuclear power plants, which comprise of thousands of systems and components that work systematically together for the purpose of generating electricity in a safe, economical and environmentally friendly manner. As the instrumentation and electrical components advance and become more sophisticated and migrate from analog design to the more complicated and error-prone software-based topology, the task of determining that a programmable electronic system (PES) is capable of meeting its safety-related design objective becomes ever more challenging. The dependence on the PES to accomplish its safety-related object must be thoroughly studied to assess the safety-related impacts associated with the potential failure modes of the device. Application Specific Product Qualification (ASPQ) is used to provide neccessay aasurance in the design integrity of a PES and confirms that the product can meet the requirements of a safety-related application. This report is an application specific product qualification (ASPQ) assessment of WEP 1010-110/120-NEA and WEP 1020-110/120-NEA Uninterruptible Power Supplies manufactured by Gambit Electronic Ltd. Information referenced in this report is based on the data received from Gambit, other nuclear power plants using Gambit products and the site visit paid to Gambit, Country-X in August 2007. Gambit WEP 1010- and 10XX-XXX/YY NEA UPS systems are used to provide uninterruptible Class II power to a number of safety-related control and instrumentation power distribution panels for R1 and R2 reactors located in X facility. These UPS are commercial Off-the Shelf (COTS) products intended for industrial uninterruptible power supply applications. An earlier Categorization Assessment Report concluded that UPS perform Category B safety-related functions and therefore, they must be qualified to meet the safety requirements associated with a Class BProgrammable Electronic System (PES) as per IEC 61513.A combination of methods were utilized to demonstrate that the UPS systems were suitable for the target applications, were inherently correct in design, and came with sufficient documentation to allow safe operation by the plant. The key findings of this report indicate that the aforementioned UPS systems are suitable for use in the target application, have strong evidence of reliability through field experience and various product certifications that support correctness of their design and come with thorough documentation that support safe operation and suitability assessment. Two major recommendations made in this report are to establishing a Preventive Maintenance (PM) program by the station to perform replacement of life-limiting components at the minimum frequencies specified by the manufacturerer, and to set ip an inspection and testing program by the station to perform minimum -monthly testing of the output power quality of the UPS systems to minimize the possibility of partial failure, which is the failure of concern and relates to a situation where the loads are supplied with out-of-specification power, undetected.


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