Research Concept of Decommissioning Knowledge Management for the Fugen NPP

2018 ◽  
Author(s):  
Yasuyoshi Taruta ◽  
Satoshi Yanagihara ◽  
Yukihiro Iguchi ◽  
Koichi Kitamura ◽  
Masashi Tezuka ◽  
...  
Keyword(s):  
Knowledge Management ◽  
Semantic Web ◽  
Nuclear Power ◽  
Nuclear Reactor ◽  
Good Method ◽  
Nuclear Facilities ◽  
Energy Agency ◽  
The World ◽  
Research Concept ◽  
Construction Operation

In 2002, the International Atomic Energy Agency (IAEA) mentioned the strengthening of nuclear knowledge, technology and application. This background has that there are aging of nuclear facility and nuclear power plant staffs. In addition, it would be difficult to succession a nuclear knowledge, technology, and skills. For example, undergraduate departments of nuclear energy and science are decreasing. The IAEA discussing those situations and pointed out the importance of a nuclear knowledge management. The nuclear knowledge management (NKM) is developing a database science as management on nuclear knowledge and information. In recent years, the IAEA has also advanced knowledge taxonomies on nuclear accidents as one of a nuclear knowledge management. In Japan, this achievements of nuclear knowledge taxonomy was using in the organization of information on accidents in Fukushima. A few studies are attempts to appropriately arrange and utilize huge amounts of information. Even in nuclear facilities in Japan, it is pointed out a veteran or expert staff retirement and loss of knowledge and skill caused by this retirement. This problem is common issue in the world. Then, we created a prototype database system to utilize past documentation of knowledge and information. The database made from semantic web technology. The semantic web is a method of preparing a frame of categorized knowledge and linking information related to it. The target is a nuclear reactor of ATR Fugen that is decommissioning from 2008. Until now, cases of decommissioning completion are 17 cases in the world. One case of JPDR in Japan. It is not enough to understand a good method of decommissioning. In general, the decommissioning project requires many information related to dismantling and decontamination. Particular, past information is important to know a past contamination situation and so on. This study focus on an access method for past data and information. However, we need to pay attention to other side of decommissioning project. Because of history of operating reactor has different tasks that are design, construction, operation and decommissioning. It is not appropriate to use the collected information as it is. For that reason, we will continue our research on the points pointed out above.

Consideration of Relationship Between Decommissioning With Digital-Twin and Knowledge Management

2020 ◽  
Author(s):  
Yasuyoshi Taruta ◽  
Satoshi Yanagihara ◽  
Takashi Hashimoto ◽  
Shigeto Kobayashi ◽  
Yukihiro Iguchi ◽  
...  
Keyword(s):  
Knowledge Management ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Digital Technology ◽  
Nuclear Power ◽  
Next Generation ◽  
Digital Twin ◽  
Advanced Technologies ◽  
The World

Abstract Decommissioning of Nuclear Power Plant is a long-term project during which generations are expected to change. Therefore, it is necessary to appropriately transfer knowledge, technology and skills to the next generation. In recent years, in the world of decommissioning, attempts have been made to apply advanced technologies such as utilization of knowledge management and digital technology. This study describes adaptation in decommissioning from viewpoint of utilizing IT technology called digital twin and aspect of knowledge management.

scholarly journals Of Broken Seals and Broken Promises: Attributing Intention at the IAEA

2019 ◽  
Vol 34 (4) ◽  
Author(s):  
Anna Weichselbraun
Keyword(s):  
International Law ◽  
Global Politics ◽  
Nuclear Safeguards ◽  
Nuclear Facilities ◽  
Energy Agency ◽  
International Crisis ◽  
Negotiated Agreements ◽  
Binary Signal ◽  
The World ◽  
The Relationship

In the world of global politics, talk is cheap. States sign negotiated agreements, but a treaty without an enforcement mechanism is considered weak, because states are not expected to adhere to commitments whose materiality is merely that of ink and paper. To verify the terms of state commitments to the Treaty on the Non-proliferation of Nuclear Weapons, which entered into force in 1970, International Atomic Energy Agency (IAEA) nuclear safeguards inspectors place tamper-evident seals in nuclear facilities. While seals appear to work simply as a binary signal, their meanings are multivalent. This article draws on fieldwork at the IAEA, and on broken seals in Iran between 2004 and 2006 that escalated into an international crisis, to examine the relationship between the material properties of the seal and its signifying potentialities. Bringing the perspective of semiotic ontology to the question of materiality, this essay argues that seals constitute a semiotic infrastructure of nuclear governance that materializes international law.

scholarly journals A Hydrogen Ignition Mechanism for Explosions in Nuclear Facility Piping Systems

2013 ◽  
Vol 135 (5) ◽  
Author(s):  
Robert A. Leishear
Keyword(s):  
Nuclear Power ◽  
Nuclear Reactor ◽  
Nuclear Industry ◽  
Ignition Source ◽  
Piping System ◽  
Nuclear Facilities ◽  
Piping Systems ◽  
Fluid Transients ◽  
Hydrogen Ignition ◽  
Explosion Mechanism

Hydrogen explosions may occur simultaneously with fluid transients' accidents in nuclear facilities, and a theoretical mechanism to relate fluid transients to hydrogen deflagrations and explosions is presented herein. Hydrogen and oxygen generation due to the radiolysis of water is a recognized hazard in piping systems used in the nuclear industry, where the accumulation of hydrogen and oxygen at high points in the piping system is expected, and explosive conditions may occur. Pipe ruptures in nuclear reactor cooling systems were attributed to hydrogen explosions inside pipelines, i.e., Hamaoka, Nuclear Power Station in Japan, and Brunsbuettel in Germany (Fig. 1Fig. 1Hydrogen explosion damage in nuclear facilities Antaki, et al. [9,10–12] (ASME, Task Group on Impulsively Loaded Vessels, 2009, Bob Nickell)). Prior to these accidents, an ignition source for hydrogen was not clearly demonstrated, but these accidents demonstrated that a mechanism was, in fact, available to initiate combustion and explosion. A new theory to identify an ignition source and explosion cause is presented here, and further research is recommended to fully understand this explosion mechanism. In fact, this explosion mechanism may be pertinent to explosions in major nuclear accidents, and a similar explosion mechanism is also possible in oil pipelines during off-shore drilling.

scholarly journals The Efficacy of the Global Nuclear Security Legal Regime and States’ Implementation Capacity in Light of the Forthcoming Development of Advanced Nuclear Reactor Technologies

Nuclear Law ◽  
2022 ◽  
pp. 161-171
Author(s):  
Bonnie Denise Jenkins
Keyword(s):  
Nuclear Reactor ◽  
Nuclear Material ◽  
Legal Framework ◽  
Nuclear Facilities ◽  
Legal Regime ◽  
Energy Agency ◽  
Physical Protection ◽  
Regulatory Standards ◽  
Nuclear Security ◽  
Implementation Capacity

AbstractThe forthcoming arrival of small modular reactors and other advanced nuclear reactor technologies can be an immensely beneficial development in the world’s collective pursuit of energy security and meeting climate change objectives. The key question is whether or not these new reactor technologies significantly alter the fundamental premises underlying the existing nuclear security legal regime. The Convention on the Physical Protection of Nuclear Material and its Amendment (A/CPPNM) are the only legally binding international instruments governing the physical protection of nuclear materials and nuclear facilities. Together the A/CPPNM and the international guidance on nuclear security comprise the current legal framework for nuclear security. This chapter examines whether the A/CPPNM adequately covers advanced reactor technologies; and whether the States that are interested in acquiring these new reactor technologies have the capacity to effectively implement the associated legal requirements, regulatory standards, and international guidance that comes along with such technologies. The analysis touches upon the role of the International Atomic Energy Agency (IAEA), the IAEA Nuclear Security Guidance, and issues of cybersecurity.

scholarly journals The Work Results of the Institute for Safety Problems of Nuclear Power Plants of the NAS of Ukraine in 2020

2021 ◽  
Vol 20 ◽  
pp. 96-105
Author(s):  
V. S. Havrylenko ◽  
◽  
I. V. Kutsyna ◽  
D. I. Кhvalin ◽  
◽  
...  
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Spent Nuclear Fuel ◽  
Scientific Work ◽  
Development Effort ◽  
Nuclear Facilities ◽  
Energy Agency ◽  
Public Authorities ◽  
Organizational Activities

The year 2020 has become a real challenge for almost all aspects of life all over the world. Under these conditions, Ukrainian science, which has been in a state of crisis for more than a year, has been forced to overcome additional difficulties. However, due to the efforts of scientists, scientific work not only did not stop, but also received a large development effort in new directions and formats. In 2020, the Institute for Safety Problems of Nuclear Power Plants was one of the scientific institutions that under the new conditions made every effort to carry out the planned scientific researches and perform works in accordance with its activities. The main results of scientific and scientific-organizational activities of the Institute for Safety Problems of Nuclear Power Plants in 2020 are presented in the article. Despite the difficult economic situation due to the epidemic, the staff of the Institute obtained important results in studies of nuclear and radiation safety of the Shelter object, and in works aimed at improving the reliability and safety of existing Ukrainian and foreign nuclear power plants. The results of works in the field of the Shelter object transformation into an ecologically safe system, safe operation of nuclear facilities, decommissioning of nuclear facilities, spent nuclear fuel and radioactive waste management are presented in the article. The results of the work performed under the International Atomic Energy Agency (IAEA) grant and the Ukrainian-Japanese Science and Technology Research Partnership for Sustainable Development (SATREPS) project are described. The implementation of the results of these studies in practice is indicated. Scientific and expert activities in the interests and at the request of public authorities, cooperation with national and foreign scientific organizations as well as scientific and organizational activities in 2020 are described. Information on internal certification of employees, participation in international and national events, publishing and etc. is presented.

Bayesian Analysis of Piping Leak Frequency Using OECD/NEA Data

2010 ◽  
Vol 132 (7) ◽  
Author(s):  
Min Wang ◽  
Mahesh D. Pandey ◽  
Jovica R. Riznic
Keyword(s):  
Failure Rate ◽  
Nuclear Power ◽  
The United States ◽  
Bayesian Procedure ◽  
Two Stage ◽  
Energy Agency ◽  
Failure Frequency ◽  
Nuclear Plants ◽  
Consistent Manner ◽  
Construction Operation

The estimation of piping failure frequency is an important task to support the probabilistic risk analysis and risk-informed in-service inspection of nuclear power plant systems. This paper describes a hierarchical or two-stage Poisson-gamma Bayesian procedure and applies this to estimate the failure frequency using the Organization for Economic Co-operation and Development/Nuclear Energy Agency pipe leakage data for the United States nuclear plants. In the first stage, a generic distribution of failure rate is developed based on the failure observations from a group of similar plants. This distribution represents the interplant (plant-to-plant) variability arising from differences in construction, operation, and maintenance conditions. In the second stage, the generic prior obtained from the first stage is updated by using the data specific to a particular plant, and thus a posterior distribution of plan specific failure rate is derived. The two-stage Bayesian procedure is able to incorporate different levels of variability in a more consistent manner.

scholarly journals Safety Assessment of Low-Contaminated Equipment Dismantling at Nuclear Power Plants

2015 ◽  
Vol 2015 ◽  
pp. 1-11 ◽  
Author(s):  
Egidijus Babilas ◽  
Eugenijus Ušpuras ◽  
Sigitas Rimkevičius ◽  
Gintautas Dundulis ◽  
Mindaugas Vaišnoras
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Safety Assessment ◽  
Power Plants ◽  
Structural Integrity ◽  
Building Structures ◽  
Nuclear Facilities ◽  
Energy Agency ◽  
Force Calculation

The decommissioning of nuclear facilities requires adequate planning and demonstration that dismantling and decontamination activities can be conducted safely. Existing safety standards require that an appropriate safety assessment be performed to support the decommissioning plan for each facility (International Atomic Energy Agency, 2006). This paper presents safety assessment approach used in Lithuania during the development of the first dismantling and decontamination project for Ignalina NPP. The paper will mainly focus on the identification and assessment of the hazards raised due to dismantling and decontamination activities at Ignalina Nuclear Power Plant and on the assessment of the nonradiological and radiological consequences of the indicated most dangerous initiating event. The drop of heavy item was indicated as one of most dangerous initiating events for the discussed Ignalina Nuclear Power Plant dismantling and decontamination project. For the analysis of the nonradiological impact the finite element model for the load drop force calculation was developed. The radiological impact was evaluated in those accident cases which would lead to the worst radiological consequences. The assessments results show that structural integrity of the building and supporting columns of building structures will be maintained and radiological consequences are lower than the annual regulatory operator dose limit.

scholarly journals An Ounce of Prevention—A Pound of Cure? The Reagan Administration’s Nonproliferation Policy and the Osirak Raid

2021 ◽  
pp. 4-40
Author(s):  
Giordana Pulcini ◽  
Or Rabinowitz
Keyword(s):  
United States ◽  
Foreign Policy ◽  
International Atomic Energy Agency ◽  
Nuclear Reactor ◽  
The United States ◽  
Atomic Energy ◽  
Nuclear Nonproliferation ◽  
Political Strategy ◽  
Energy Agency ◽  
The World

The Israeli raid in June 1981 against the Osirak nuclear reactor in Iraq has been extensively analyzed by scholars, especially in the context of debate about the efficacy of preemptive strikes against hostile nuclear programs. Yet surprisingly, some important historical questions have been left unanswered: how did the raid affect the Reagan administration’s nuclear nonproliferation policy, and how was the raid perceived by relevant administration officials? How did the United States design its political strategy of response to the raid, and how did this strategy play out at the International Atomic Energy Agency? What does this episode tell us about Ronald Reagan’s foreign policy priorities? By exploring recently declassified documents from several archives around the world, this article addresses all of these questions and, in the process, debunks revisionist myths relating to the raid.

A Review on Specific Features of Small and Medium Sized Nuclear Power Plants

2010 ◽  
Author(s):  
Salah Ud-din Khan ◽  
Minjun Peng ◽  
Muhammad Zubair ◽  
Shaowu Wang
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Reactor ◽  
Nuclear Reactors ◽  
Fixed Bed ◽  
Nuclear Industry ◽  
Energy Agency ◽  
Pressurized Water ◽  
Water Reactor ◽  
Energy Supply System

Due to global warming and high oil prices nuclear power is the most feasible solution for generating electricity. For the fledging nuclear power industry small and medium sized nuclear reactors (SMR’s) are instrumental for the development and demonstration of nuclear reactor technology. Due to the enhanced and outstanding safety features, these reactors have been considered globally. In this paper, first we have summarized the reactor design by considering some of the large nuclear reactor including advanced and theoretical nuclear reactor. Secondly, comparison between large nuclear reactors and SMR’s have been discussed under the criteria led by International Atomic Energy Agency (IAEA). Thirdly, a brief review about the design and safety aspects of some of SMR’s have been carried out. We have considered the specifications and parametric analysis of the reactors like: ABV which is the floating type integral Pressurized water reactor; Long life, Safe, Simple Small Portable Proliferation Resistance Reactor (LSPR) concept; Multi-Application Small Light Water Reactor (MASLWR) concept; Fixed Bed Nuclear Reactor (FBNR); Marine Reactor (MR-X) & Deep Sea Reactor (DR-X); Space Reactor (SP-100); Passive Safe Small Reactor for Distributed energy supply system (PSRD); System integrated Modular Advanced Reactor (SMART); Super, Safe, Small and Simple Reactor (4S); International Reactor Innovative and Secure (IRIS); Nu-Scale Reactor; Next generation nuclear power plant (NGNP); Small, Secure Transportable Autonomous Reactor (SSTAR); Power Reactor Inherently Safe Module (PRISM) and Hyperion Reactor concept. Finally we have point out some challenges that must be resolved in order to play an effective role in Nuclear industry.

Technologies Used for D&D of the A-1 NPP in Slovakia and Their Comparison With Advanced Worldwide Approaches

2001 ◽  
Author(s):  
Kamil Kravárik ◽  
Vladimír Míchal ◽  
Peter Menyhardt
Keyword(s):  
Radioactive Waste ◽  
Nuclear Power ◽  
Power Plants ◽  
Slovak Republic ◽  
Liquid Radioactive Waste ◽  
Nuclear Regulatory Commission ◽  
Technical Level ◽  
Nuclear Facilities ◽  
Energy Agency ◽  
Regulatory Commission

Abstract This paper deals with technologies used for decommissioning and decontamination of the A-1 Nuclear Power Plant in Slovakia and their comparison with advanced worldwide approaches. Present status and main results in the field of D&D of this first Czechoslovak NPP A-1 at Jaslovské Bohunice are described. NPP A-1 has one unit with reactor cooled by CO2 and moderated by heavy water. Plant was in operation from 1972 to 1977 and its final shutdown and closure were done due to relatively serious accident. The A-1 NPP Decommissioning Project – I. phase is performed at the present time and represents the most important project of NPP decommissioning in Central Europe. The main goal of the project is to achieve radiologically safe status of the NPP. It includes following activities: • conditioning, storage and disposal of liquid radioactive waste, solid and metallic radioactive waste, sludge and sorbents, • development, manufacture and verification of advanced methodologies and technologies for D&D of nuclear facilities, • decontamination of specified equipment and structures to reduce free activity, • technical support and preparation of following phases within the A-1 NPP overall decommissioning process. The project should give the complex solution of problems related to decommissioning and decontamination of NPPs in Slovakia. Verified methodology and technology should be used as a generic approach for decommissioning of the V-1, V-2 (Jaslovské Bohunice) and Mochovce Nuclear Power Plants as well as the other European NPPs with WWER reactors. Significant part of paper deals with following issues within D&D of the A-1 NPP: • computer aided technologies, • decontamination, • dismantling, demolishing and remote handling manipulators, • dosimetry measurements within D&D, • radioactive waste management. This paper also includes basic comparison with advanced worldwide approaches to decommissioning and decontamination mainly in USA, Japan and West Europe and the recommendations are done when it is possible. The comparison shows that trends in the field of D&D in the Slovak Republic are compatible and comparable with the most significant world trends. It is noted that some sorts of D&D technologies like for example telerobotic systems developed in the world are at the relatively higher technical level. Decommissioning technologies in Slovakia should be permanently improved on the base of experiences from home and abroad industry and from the real operation. It is supposed that after short time could be achieved technical level comparable with the best D&D robots and manipulators. A basic strategy of NPP decommissioning in the Slovak Republic is regulated by standards, which are in accordance with recommendations of international bodies like the International Atomic Energy Agency, European Commission, U.S. Nuclear Regulatory Commission, OECD Nuclear Energy Agency etc. In the field of NPP D&D the Slovak Republic co-operates with many international organizations and also with main active countries in D&D like Germany, France, Belgium, Great Britain, USA, Japan, Russian Federation, Hungary, Poland and Czech Republic. Intensive international co-operation at all levels has already been established at the present time.

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