Cable Tray Ultimate Strength Test Employing a Large Shaker Table

Author(s):  
Kuniyoshi Komatsu ◽  
Katsunori Myojin ◽  
Hiroyuki Fuyama ◽  
Eiji Kokubo ◽  
Kazuo Imai

Ultimate behaviors of cable trays, used in nuclear plants, have not been well studied since cable trays are designed based on conservative design criteria. In this study, by employing a large shaker table, an ultimate strength test was conducted for cable trays used in nuclear power plants. This report describes the results of shaker table test. The following results were obtained: 1) In an S2* earthquake, the damping ratio was so large — more than 30% due to the rubbing of cables — that a large response was not present and the strains in the support were within the elastic limits. 2) The support was strong enough to sustain the cable trays even when the strain in the support was 20 times larger than elastic strain.

2020 ◽  
Vol 20 (2) ◽  
pp. 127-132
Author(s):  
Namjin Cho ◽  
Dongsu Im ◽  
Jungdon Kwon ◽  
Teayeon Cho ◽  
Junglim Lee

Nuclear power plants store and use flammable gases and liquids and consequently risk explosions. Therefore, nuclear plants employ explosion-proof equipment; however, this equipment is not always sufficiently maintained. This lack of maintenance can affect the safety-related equipment intended to shut down the reactor, because the explosion-proof equipment itself can act as an ignition source. Radio-frequency identification (RFID) technology should be explored as a tool to improve both the convenience and efficiency of maintenance. We analyzed and compared explosion-proof RFID technology that can be used in nuclear power plants.


Author(s):  
Keisuke Minagawa ◽  
Satoshi Fujita ◽  
Seiji Kitamura ◽  
Shigeki Okamura

This paper describes the dynamic strength evaluation of piping installed in nuclear power plants from a viewpoint of energy balance. Mechanical structures installed in nuclear power plants such as piping and equipment are usually designed statically in elastic region. Although these mechanical structures have sufficient seismic safety margin, comprehending the ultimate strength is very important in order to improve the seismic safety reliability in unexpected severe earthquakes. In this study, ultimate strength of a simple single-degree-of-freedom model is investigated from a viewpoint of energy balance equation that is one of valid methods for structural calculation. The investigation is implemented by forced vibration experiment. In the experiment, colored random wave having predominant frequency that is similar to natural frequency of the experimental model is input. Stainless steel and carbon steel are selected as material of experimental model. Excitation is continued until the experimental model is damaged, and is carried out with various input levels. As a result of the experiment, it is confirmed that input energy for failure increase with an increase of time for failure. Additionally it is confirmed that input energy for failure depend on the material.


2002 ◽  
Vol 13 (2) ◽  
pp. 239-261
Author(s):  
Steve Thomas

In 1990, the privatisation of the British electricity supply industry revealed how uneconomic Britain's nuclear power plants were. The nuclear sector was withdrawn from privatisation and it seemed likely that by 2000, most of Britain's nuclear power plants would be closed. However, operating costs were dramatically reduced and in 1996, most of the nuclear plants were privatised in British Energy. Nuclear output made an important contribution to the reduction of greenhouse gas emissions and the future looked secure for the existing plants. However, the early success of British Energy was based on an inflated wholesale electricity price and by 2000, British Energy was struggling to cover its costs. The British government is now conducting a review of energy policy. The economic case for new nuclear power plants is poor but the need to meet greenhouse gas emission targets and the influence British Energy and BNFL may ensure the long-term future of the existing plants.


2021 ◽  
Vol ahead-of-print (ahead-of-print) ◽  
Author(s):  
Akponanabofa Henry Oti ◽  
Peter Farrell ◽  
Fonbeyin Henry Abanda ◽  
Paul McMahon ◽  
Abdul-Majeed Mahamadu ◽  
...  

Purpose The relatively low capital cost and contributions to mitigating global warming have favoured the continuous construction and operation of nuclear power plants (NPPs) across the world. One critical phase in the operation of nuclear plants for ensuring the safety and security of radioactive products and by-products is decommissioning. With the advent of digital twinning in the building information modelling (BIM) methodology, efficiency and safety can be improved from context-focus access to regulations pertaining to demolition of structures and the cleaning-up of radioactivity inherent in nuclear stations. The purpose of this study, therefore, is to propose a BIM-driven framework to achieve a more regulation-aware and safer decommissioning of nuclear power plants. Design/methodology/approach The framework considers task requirements, and landscape and environmental factors in modelling demolition scenarios that characterise decommissioning processes. The framework integrates decommissioning rules/regulations in a BIM linked non-structured query system to model items and decommissioning tasks, which are implemented based on context-focussed retrieval of decommissioning rules and regulations. The concept’s efficacy is demonstrated using example cases of digitalised NPPs. Findings This approach contributes to enhancing improvements in nuclear plant decommissioning with potential for appropriate activity sequencing, risk reduction and ensuring safety. Originality/value A BIM-driven framework hinged on querying non-structured databases to provide context-focussed access to nuclear rules and regulations and to aiding decommissioning is new.


Author(s):  
Anne-Sophie Bogaert ◽  
Michel Desmet ◽  
Arnaud Gendebien

Since the Surry-accident of 1986, Electrabel and Tractebel Engineering have performed extensive ultrasonic inspection campaigns to detect pipe wall thinning due to Flow Accelerated Corrosion (FAC) in the Balance-of-Plant systems of the seven Belgian nuclear power plants. Since 2000 EPRI’s predictive software CHECWORKS is used as a means to focus future inspections on the most susceptible components. In 2005, Tractebel Engineering participated in a benchmark set-up by the Framatome Owners Group (FROG) that compared the different FAC predictive models used by the FROG members. In 2006, Electrabel and Tractebel Engineering decided to perform an assessment of the way in which the follow-up of Flow Accelerated Corrosion (FAC) is done in the Belgian nuclear plants. This paper summarizes the Flow Accelerated Corrosion program in the Belgian nuclear plants as well as some of the main aspects of the Flow Accelerated Corrosion management, including the use of a predictive software, the method of inspections and the actions taken to keep the FAC program up to date.


Author(s):  
Toru Iijima ◽  
Masaki Nakagawa ◽  
Akira Shibuya ◽  
Katsumi Ebisawa ◽  
Hiroyuki Kameda

In Japan, the Seismic Design Guideline for Nuclear Power Plants revised in 2006 requires that residual risk for earthquakes beyond design base be considered. Moreover, in the Niigata-ken Chuetsu-oki earthquake (NCOE:2007), the earthquake motion exceeded the seismic design condition of the Kashiwazaki-Kariwa nuclear power plants (KK NPPs). In response to these issues, there is a growing demand for quantitative clarification of seismic safety margin. The Japan Nuclear Energy Safety Organization (JNES) started a study on the seismic safety margin. JNES defined the term “seismic safety margin” in this study. The seismic safety margin is based on the probability distribution of seismic response and seismic capacity of equipment. Regarding the seismic capacity, JNES has carried out seismic capacity tests on various types of equipment whose malfunction would significantly affect core damage frequency in terms of seismic probabilistic safety assessment (seismic PSA). Our seismic safety margin is effective to understand the quantitative margin related to the failure of equipment. JNES applied the concept of seismic safety margin to thin wall cylindrical tanks utilizing ultimate strength test results, and compared it with the design margin. This paper reports examples of the seismic margin evaluation of cylindrical tank.


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