Hitachi-GE Advanced Construction Management Technologies

Author(s):  
Kimiharu Onda ◽  
Masatoshi Takada ◽  
Hisako Okada ◽  
Kazuto Tatehora

Hitachi has so far developed the construction management system with information technology since more than twenty years ago. As the recent results, we developed the advanced new functions and applied them to the Nuclear Power Plant (NPP)’s under construction. RFID-applied construction management method with personal digital assistant (PDA) could realize more reliable and efficient construction control on a site. By enhancing an Integrated Schedule Planning function, the construction scheme could be more accurately and speedily developed, which made it possible to realize the standardization of schedule planning, the linkage with other systems, and the improvement of operability. By applying these new technologies to Hitachi construction management, Hitachi can supply the nuclear power plant with higher quality, safety, and reliability.

2021 ◽  
Vol 11 (1) ◽  
Author(s):  
Toshihiro Horiguchi ◽  
Kayoko Kawamura ◽  
Yasuhiko Ohta

AbstractIn 2012, after the accident at the Fukushima Daiichi Nuclear Power Plant (FDNPP) that followed the Tohoku earthquake and tsunami in March 2011, no rock shell (Thais clavigera; currently recognized as Reishia clavigera; Gastropoda, Neogastropoda, Muricidae) specimens were found near the plant from Hirono to Futaba Beach (a distance of approximately 30 km). In July 2016, however, rock shells were again found to inhabit the area. From April 2017 to May 2019, we collected rock shell specimens monthly at two sites near the FDNPP (Okuma and Tomioka) and at a reference site ~ 120 km south of the FDNPP (Hiraiso). We examined the gonads of the specimens histologically to evaluate their reproductive cycle and sexual maturation. The gonads of the rock shells collected at Okuma, ~ 1 km south of the FDNPP, exhibited consecutive sexual maturation during the 2 years from April 2017 to May 2019, whereas sexual maturation of the gonads of specimens collected at Hiraiso was observed only in summer. The consecutive sexual maturation of the gonads of the specimens collected at Okuma might not represent a temporary phenomenon but rather a site-specific phenotype, possibly caused by specific environmental factors near the FDNPP.


Author(s):  
Sun Na ◽  
Shi Gui-lian ◽  
Xie Yi-qin ◽  
Li Gang ◽  
Jiang Guo-jin

Communication independence is one of the key criteria of digital safety I&C system design. This paper mainly analyzes the requirements for communication independence in safety regulations and standards, and then introduces the architecture and design features, including communication failure processing measures, of communication networks of ACPR1000 nuclear power plant safety digital protection system based on FirmSys platform developed by CTEC. The communication design meets the regulations requirements and effectively improves the safety and reliability of the system, and it is successfully applied in reactor protection system (RPS) of Yang Jiang nuclear power plant unit 5&6. In addition this design can provide reference for communication designs of other NPPs and industries.


Author(s):  
Kenji Akagi ◽  
Masayuki Ishiwata ◽  
Kenji Araki ◽  
Jun-Ichi Kawahata

In nuclear power plant construction, countless variety of parts, products, and jigs more than one million are treated under construction. Furthermore, strict traceability to the history of material, manufacturing, and installation is required for all products from the start to finish of the construction, which enforce much workforce and many costs at every project. In an addition, the operational efficiency improvement is absolutely essential for the effective construction to reduce the initial investment for construction. As one solution, RFID (Radio Frequent Identification) application technology, one of the fundamental technologies to realize a ubiquitous society, currently expands its functionality and general versatility at an accelerating pace in mass-production industry. Hitachi believes RFID technology can be useful of one of the key solutions for the issues in non-mass production industry as well. Under this situation, Hitachi initiated the development of next generation plant concept (ubiquitous plant construction technology) which utilizes information and RFID technologies. In this paper, our application plans of RFID technology to nuclear power is described.


Author(s):  
Iurii G. Smirnov ◽  
◽  
Aleksandr O. Orlov ◽  

Introduction. The construction of underground installations in permafrost is aimed at ensuring the integrated safety of power facilities, small nuclear power plants (SNPP). In these conditions, location choice is a crucial stage in SNPP design and construction. As a rule, construction sites are situated at remote and little developed territories. Construction in permafrost is characterized by adverse climatic conditions and frozen soil, which lead to construction cost indicators growth. Research aim is to carry out comparative evaluation of two sites available for the facilities arrangement at the Peschanka copper porphyry deposit by ranking SNPP location sites. Methodology. Natural and climatic conditions play a significant role in siting and are capable of affecting the safety of both the nuclear facility and surrounding territories during a nuclear power plant operation. The choice of the station location is associated with a number of natural and man-made environmental characteristics. Results. The determining factor in the use of the energy sources under consideration is the need to bring them closer to the main energy consumers, especially in remote and hard-to-reach areas without developed infrastructure. As part of SNPP creation concept, there is an increasing significance of research concerning the siting of underground radiation-hazardous facilities. The methodical approach to selecting sites for underground installations in permafrost includes their ranking. Summary. While ranking the sites according to natural and socio-economic criteria, the most acceptable sites for SNPPs are identified. The results of research on the choice of particular sites during the construction of a mining and processing complex at Peschanka deposit have made it possible to make a conclusion on the site’s suitability for underground installation adit location.


2013 ◽  
Vol 13 (11) ◽  
pp. 30287-30309 ◽  
Author(s):  
T. Christoudias ◽  
Y. Proestos ◽  
J. Lelieveld

Abstract. We estimate the global risk from the release and atmospheric dispersion of radionuclides from nuclear power plant accidents using the EMAC atmospheric chemistry–general circulation model. We included all nuclear reactors that are currently operational, under construction and planned or proposed. We implemented constant continuous emissions from each location in the model and simulated atmospheric transport and removal via dry and wet deposition processes over 20 yr (2010–2030), driven by boundary conditions based on the IPCC A2 future emissions scenario. We present global overall and seasonal risk maps for potential surface layer concentrations and ground deposition of radionuclides, and estimate potential dosages to humans from the inhalation and the exposure to ground deposited radionuclides. We find that the risk of harmful doses due to inhalation is typically highest during boreal winter due to relatively shallow boundary layer development and reduced mixing. Based on the continued operation of the current nuclear power plants, we calculate that the risk of radioactive contamination to the citizens of the USA will remain to be highest worldwide, followed by India and France. By including stations under construction and those that are planned and proposed our results suggest that the risk will become highest in China, followed by India and the USA.


Author(s):  
Laiye Zhu ◽  
Maogang Zhu ◽  
Yanhong He ◽  
Xin Wang ◽  
Wenshu Dong

With the introduction of third generation of nuclear power AP1000, Westinghouse uses the mobile device (a mobile wastewater treatment device 6 units shared) radioactive waste system design concepts. This design not only simplifies the process of nuclear island waste system; saves equipment layout space; improves equipment utilization; while increases the use of new technologies lifetime of the plant and the possibility of flexibility. This paper introduces the first AP1000 unit (Sanmen, Zhejiang Province) by using the advanced mobile device technology and application of wastewater treatment under the condition of the primary coolant source level. At the same time, the paper also discusses the periodic system inspection and the strategy of maintenance. In addition, the paper further expands the application direction of the mobile waste processing aspects, such as: decommissioning of nuclear facilities; enhancing the facility decommissioning radioactive liquid waste purification capability. Another example: After the Fukushima accident, people pay more attention to accident-mitigation-design and hope to accelerate the development of emergency radioactive liquid waste processing devices. Thus, in addition to strengthening the nuclear power plant inherent defense in depth and resistance emergency capability, mobile waste treatment device or combination device special regional settings can be made to improve and enhance the ability to get more diversified emergency response.


2014 ◽  
Vol 617 ◽  
pp. 81-85 ◽  
Author(s):  
Juraj Králik ◽  
Juraj Kralik

Safety and reliability of the communication steel bridge of the nuclear power plant under extreme loads is considered in this paper. The extreme load from the wind and the earthquake is defined for the probability of exceedance 10-4 per year on the base of the last results from the investigation in Slovakia. The deterministic and the probabilistic assessments to verify the safety and reliability of the structure are presented. The uncertainties of the input data and the calibration of the load factors are discussed. The advantages and disadvantages of the probabilistic analysis are discussed. The advantages of the utilization the LHS method to analyze the safety and reliability of the structures is presented.


2014 ◽  
Vol 14 (9) ◽  
pp. 4607-4616 ◽  
Author(s):  
T. Christoudias ◽  
Y. Proestos ◽  
J. Lelieveld

Abstract. We estimate the global risk from the release and atmospheric dispersion of radionuclides from nuclear power plant accidents using the EMAC atmospheric chemistry–general circulation model. We included all nuclear reactors that are currently operational, under construction and planned or proposed. We implemented constant continuous emissions from each location in the model and simulated atmospheric transport and removal via dry and wet deposition processes over 20 years (2010–2030), driven by boundary conditions based on the IPCC A2 future emissions scenario. We present global overall and seasonal risk maps for potential surface layer concentrations and ground deposition of radionuclides, and estimate potential doses to humans from inhalation and ground-deposition exposures to radionuclides. We find that the risk of harmful doses due to inhalation is typically highest in the Northern Hemisphere during boreal winter, due to relatively shallow boundary layer development and limited mixing. Based on the continued operation of the current nuclear power plants, we calculate that the risk of radioactive contamination to the citizens of the USA will remain to be highest worldwide, followed by India and France. By including stations under construction and those that are planned and proposed, our results suggest that the risk will become highest in China, followed by India and the USA.


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