Results 1 - 9 of 9
Results 1 - 9 of 9. Search took: 0.016 seconds
|Sort by: date | relevance|
[en] Thailand Nuclear Technology Service Centre (NTSC) is a nuclear service centre under the supervision of Thailand Institute of Nuclear Technology (TINT), established in 2006. NTSC is responsible for several types of nuclear technology services, for example, analysis of samples’ compositions by using nuclear techniques, nuclear and radiation survey metres’ calibration, non-destructive testing, and to certify radiation levels of food products for exporters. NTSC has continuously maintained a high level of service quality and customer satisfaction which leads to achieving the highest growth among TINT’s service centres. Its revenue has grown more than 600% within 10 years (from $196,000 to $1.5 million). All of NTSC’s revenue is contributed back to TINT which later is distributed into TINT’s fringe benefits, incentive regimes, research instruments, and R&D projects. The circulation of this revenue, therefore, could back up TINT to secure its fundamental expenses in both organisational development and in R&D. Thus, the following questions arose, what have NTSC and its staff done to become successful? In addition, what could TINT learn from them if TINT desires to adopt NTSC management practices to other centres? Good service quality, a certified standard of services, a reasonable price, and quick response to customers’ queries are central strengths and means for differentiating NTSC from other organisations. These strengths create additional perceived value to customers and build up a recognisable brand image. Additionally, long-term direction, continuous development, i.e. in products, services and processes, knowledge on customer behaviour by a comprehensive database, NTSC’s management commitment, and strong teamwork with trust could be the factors influencing the success of the outcomes. The report concludes that technology service management becomes more an integrative discipline between nuclear technical knowledge, and business and management. It seems both tangible and intangible resources drive the value creation in this service organisation. The study of key drivers and their functions at each unit could be beneficial for the institute to accomplish and sustain the service organisation strategically. (author)
[en] The European Network for Inspection and Qualification (ENIQ) is a network dealing with the reliability and effectiveness of non-destructive testing (NDT) for nuclear power plants (NPP). ENIQ is driven by European nuclear utilities and is working mainly in the areas of qualification of NDT systems and risk-informed in-service inspection (RI-ISI). Since its establishment in 1992 ENIQ has performed two pilot studies on in-service inspection (ISI) qualification and has issued more than 50 documents. Among them are the two ENIQ framework documents, the “European Methodology for Qualification of Non-Destructive Testing” and the “European Framework Document for Risk-Informed In-Service-Inspection”, 11 recommended practices and a significant number of technical reports and discussion documents / position papers. ENIQ is recognised as one of the main contributors to today’s global qualification guidelines for ISI. It is part of the international association on R&D on Gen II / III reactors NUGENIA and has a steering committee and two sub-areas (SAs), the SA on Qualification (SAQ), which works on issues related to the qualification of ISI systems and SA on Risk (SAR), which is focused on RI-ISI. The paper provides an overview of all current and near-future activities of ENIQ, which includes revision of all ENIQ Recommended Practices, revision of the European Framework Document on RI-ISI, completion of a study on mutual recognition of ISI qualifications between countries, a project with the aim of producing an ENIQ recommended practice on how to write a good inspection procedure, a recently completed study on the achievable level of risk reduction via ISI and a planned project for a full scope RI-ISI of a NPP. (author)
[en] To control the specific activity of 226Ra in building materials of operated buildings, a non-destructive in situ method consisted in measurements of gamma spectra with a fixed geometry of the detector position in a room is suggested. The calculation of the average specific activity of natural radionuclides in building materials is carried out by comparing the calculated flux density of unscattered gamma quanta normalized to the specific activity of 100 Bq/kg, and the experimentally measured count rates in the photopeak. For the measured values of the average specific activity of 226Ra in building materials, the expected values of radon concentration in rooms were calculated. The developed method has been verified for rooms in modern multi-storey energy-efficient buildings. Concentrations of 232Th and 40K in building materials which contribute to the indoor external radiation exposure can be measured by developed method also. (author)
[en] Long thermo-mechanical effects compounded by the environment, leads to a reduction in service properties, accelerated aging and degradation of metals in critical areas. Problems concerning violation of constructional integrity of the important equipment periodically appear during long term operation of NPP units. The most complicated and regular cases of operational damages cause necessity of development and application of new approaches on complex diagnostic of a technical condition of important NPP equipment during the whole period of a unit power operation. Center of materials Science (Russia) with cooperative MUBATEC GmbH (Germany) performed development and application in practice the methodology of multiparameter design-experimental monitoring of actual operational damageability in critical zones of the responsible NPP equipment. The methodology is intended for determination of exact causes of increased metal damageability as well as for development of effective mitigating measures. A distinctive feature of the equipment multiparameter monitoring during the reactor facility power operation consists in joining of opportunities of non-destructive inspection of metal integrity in the most critical zones, diagnostics of actual thermo-mechanical loads and calculative analysis of strength and residual lifetime of the monitored NPP equipment.
[en] The construction of the Hamaoka Nuclear Power Station Unit 1 was started in 1971, so nearly 45 years has passed until now, 2016. Its operation period was approximately 16 years and half except for the period of periodic inspections. It is currently under decommissioning which started in 2009 and will last for 28 years. Data on concrete properties of actual nuclear power plants in Japan, which were often obtained in the periodic inspections, is only limited. If huge amounts of data obtained and accumulated from the concrete structures under a decommissioning plant like the Hamaoka Nuclear Power Station Unit 1, they will be very useful to verify the nondestructive testing method/numerical analysis method and to develop the new soundness evaluation method of concrete structures. Data on the properties of concrete exposed to various environments can be obtained from decommissioning plants. In particular, it is possible to examine the heating effect on concrete exposed for a sufficiently long period (16 years) as compared with the experimental study. Core sampling of important parts such as the concrete under the irradiated conditions that cannot be sampled during the operation periods can be performed . In this report, the results of compressive strength tests of core concrete extracted from the inner wall of Hamaoka Unit 1 reactor building are presented, among the concrete physical property data currently under collecting.
[en] Malaysian Nuclear Agency (Nuklear Malaysia) established in 1972 is a premier nuclear research institute in Malaysia. The major function of Nuklear Malaysia is leading research and development in nuclear technology along with commercialisation of nuclear technology. Its operation is guided by the Malaysian Nuclear Agency Strategic Plan 2012-2020. Nuklear Malaysia hosts various major facilities and laboratories including a TRIGA PUSPATI research reactor (RTP), Gamma Green House, Electron Beam Facility and Secondary Standard Dosimetry Laboratory. In addition, Malaysia also has a long experience in safely operating a National Waste Management Centre since 1984. At the international level, Nuklear Malaysia is recognised by the International Atomic Energy Agency (IAEA) Collaborating Centre (ICC) in Non-Destructive Testing and IAEA-ICC for Radiation Processing of Natural Polymers and Nanomaterials. Malaysia has also hosted 15 IAEA Postgraduate Educational Courses (PGEC) in Radiation Protection and the Safety of Radiation Source Safety since 2004. This paper aims at presenting opportunities and challenges faced by Nuklear Malaysia to enhance its relevance and sustainability. (author)
[en] In Japan, more than 10 nuclear power plants have been in operation for over 30 years, and the importance of maintaining and managing has been increased in addition to the design and construction. Regarding the maintenance and management of nuclear structures, we perform visual testing and soundness assessment by destructive testing in order to maintain the functions and related performance required during the service period of nuclear power plants. However, in a running plant, since obtaining concrete cores will damage the structure, a reasonable soundness assessment that minimizes the number of cores is desired. Therefore, in this research, we will obtain concrete cores from Hamaoka Unit-1, the decommissioning plant, to create a concrete database of material properties. We also employ nondestructive testing and numerical analysis method to construct a better soundness assessment method with minimized damages of the structure. (author)
[en] Over the past decade, nuclear operators have established or initiated Long Term Operation (LTO) programs for their units. Cables and Civil works structures are both considered as “passive structures” and share a common history of little number of failures during the first decades of operation and thus a relatively low level of needed maintenance actions. Nevertheless, failures occurring during the LTO period may lead to significant consequences such as automatic shutdowns and heavy works may be required with high operational constraints. The article will discuss the strategy and the tactical program to increase safety and to reduce human errors by accelerating digitalization of predictive maintenance. Digitalization of maintenance is not only a technology concern. Adaptation of on-site practices for inspection, non-destructive testing and decision-making processes are required and need to be anticipated. The article shares a successful experience of digitalization of maintenance practices with practical applications and experience feedbacks, for civil works structures and cables. Moreover, it illustrates the strength of working as a unique team when mixing skills and experience of several entities. Digitalization of maintenance highlights the benefits of implementing a holistic comprehensive ageing management program. (author)
[en] Research outline Chubu Electric Power stopped operation of Hamaoka Units-1&2 on January 30, 2009 and is currently decommissioning them. Spent fuel transportation, system decontamination and contamination investigation in Unit-1 were finished and the decommissioning shifted to dismantling phase of reactor surrounding components. In this phase, a research on material degradation using actual components in Unit-1 was started, and its outline is introduced in this section. In the future reactor area dismantling phase, Chubu is planning necessary researches on in-core components in Unit-1&2. The Japanese nuclear regulation authority has issued the special inspection rule against major degradation phenomena such as irradiation embrittlement in the reactor pressure vessel (RPV) and degradation of the concrete structures in nuclear power plants in the new regulatory standard and required electric power companies more detailed degradation management than before. As a contribution to measures to cope with the regulation, we have started a research by sampling from the actual RPV and the concrete structures in Hamaoka Unit-1 since 2014. These researches are considered to be useful for an upgrade and/or an optimization of maintenance methodology through development of new inspection methods and construction of database. In the research of the concrete structure, we aim to construct a new framework for integrity assessment focusing on member strength and building vibration characteristics, rather than conventional material strength based assessment. In order to evaluate the soundness of the reactor building, we plan to construct databases by core samplings and testing, and to verify evaluation methods by non-destructive inspection methods and numerical analysis. For this purpose, we collect actual core samples from various places in Hamaoka Unit-1 reactor building. Details are described in a separate paper. The research of RPV has been started to reconfirm current maintenance methods and confirm safety tolerance in the current structural integrity assessment by utilizing small specimen technique (Fracture toughness test by 1/6TCT specimens, Atom probe analysis by acicular specimens).