Operation Of Nuclear Facilities Research Articles

The Intersection of Advancing Technology and Human Performance

Abstract Today's sensory and processing technologies are perceptive and precise. They can discern the environment, solve complicated problems, make assessments, and learn from experience. Although they do not think the way humans do, they can replicate many human intellectual aptitudes. Throughout the last several decades, companies have implemented advanced technology and increasingly removed the human from many aspects of nuclear operation. There are many advantages to this transition, but, like any system modification, failures inevitably manifest. In the instance of this article, human errors have resulted and have accounted for several accidents at nuclear facilities in the United States due to this transition. The accidents at these facilities due to human error often result in plant shutdowns, unnecessary expenses, and have the capacity to be problematic for people, the facilities, and environments. This article explores the context surrounding the complexity of changing technologies at the nuclear facilities and the potential exacerbation of problems caused by human error when technology advancements concerning operator interaction with control systems are implemented. To understand the complexity surrounding the human interaction with advancing technologies, the concepts of human performance and human factors are examined and then the impact of these concepts within the framework of advancing technology are applied to the operation of nuclear facilities. This review draws attention to the vulnerabilities due to human error at nuclear facilities within the context of continually advancing technology and sheds insight on the role human performance and human factors have on system design and the resulting outcome.

Summary and recommendations from the workshop ‘Integrating measurements and atmospheric-dispersion modelling to enhance the UK response to radiological atmospheric releases’

Effective preparedness and response to an atmospheric release following a radiological incident relies on information concerning the source, transport and eventual removal of the contaminant. A notable improvement to emergency preparedness and response in the UK to airborne releases of radiological contaminants can be achieved through the integration of information sources, in particular environmental radiological measurements and atmospheric-dispersion modelling. A one-day workshop was organised by the UK Met Office and the University of Bristol, comprising private nuclear facility operators, public bodies, academia and others, on 6 February 2020 in Bristol, UK. The workshop reviewed the current capabilities and challenges of measurements and modelling of airborne radiological contaminants and their integration, and identified improvement pathways. This memorandum provides a summary of recommendations from the workshop.

Tort law makes a quantum leap: a review of the civil liability regime for nuclear operators in UAE law

Purpose This study aims to illustrate the special liability regime applying to a nuclear operator for damage caused to individuals, property and natural resources, after the United Arab Emirates (UAE) implemented the Vienna Convention on Civil Liability for Nuclear Damage of 1963 through Federal Law No. 4 of 2012. This paper contrasts this special regime with the default regime of civil liability set out in the UAE Civil Code. The comparison helps clarify the legal nature of nuclear operator liability, the extent of protection it affords to the parties injured in a nuclear incident, the conditions under which it obtains, as well as the different damage headings it allows. Design/methodology/approach This paper is a desk-based legal research. Findings The main novelties enshrined in the special liability regime for nuclear facility operators are the adoption of an objective approach (strict liability) and the introduction of exceptions different from those contemplated in the default regime spelled out in the UAE Civil Code, thereby affording greater protection to victims of nuclear leakages. Originality/value This paper is a first in-depth commentary of UAE Federal Law No. 4 of 2012 Concerning Civil Liability for Nuclear Damage. Considering the UAE’s dualistic approach to the implementation of international obligations, and the present lack of reliable alternative avenues towards compensation beyond private operator liability, the overview provided here will be of value to regional and international practitioners – including from neighbouring countries to the UAE (Oman, Qatar, Bahrain) – that are not currently signatories to any convention on nuclear liability.

УЧЕТ НЕОПРЕДЕЛЕННОСТЕЙ В ИСХОДНЫХ ДАННЫХ ПРИ ПРОВЕДЕНИИ РАСЧЕТОВ ЭФФЕКТИВНОГО КОЭФФИЦИЕНТА РАЗМНОЖЕНИЯ АКТИВНОЙ ЗОНЫ ИССЛЕДОВАТЕЛЬСКОЙ ЯДЕРНОЙ УСТАНОВКИ

Estimation of the error in calculations, that is caused by uncertainties in the initial data is an integral part of the nuclear facilities safety case. Nuclear safety is one of the fundamental directions in safety case. Incorrect accounting for the uncertainties in the initial data can lead to a row of negative consequences, in particular, incorrect determination of the reactivity margin in various modes of normal operation, as well as in cases of the abnormal operation of nuclear facilities. This article presents results of a research of uncertainties influence on an effective multiplication factor of research reactor PIK. The design basis accident (deliquation of the central experimental channel) was analyzed during the discussed research.

Airborne Release Fractions from Surrogate Nuclear Waste Fires Containing Lanthanide Nitrates and Depleted Uranium Nitrate in 30% Tributyl Phosphate in Kerosene

Airborne contaminants from fires containing nuclear waste represent significant health hazards and shape the design and operation of nuclear facilities. Much of the data used to formulate DOE-HDBK-3010-94, “Airborne Release Fractions/Rates and Respirable Fractions for Nonreactor Nuclear Facilities,” from the U.S. Department of Energy, were taken over 40 years ago. The objectives of this study were to reproduce experiments from Pacific Northwest Laboratories conducted in June 1973 employing current aerosol measurement methods and instrumentation, develop an enhanced understanding of particulate formation and transport from fires containing nuclear waste, and provide modeling and experimental capabilities for updating current standards and practices in nuclear facilities. A special chamber was designed to conduct small fires containing 25 mL of flammable waste containing lutetium nitrate, ytterbium nitrate, or depleted uranium nitrate. Carbon soot aerosols showed aggregates of primary particles ranging from 20 to 60 nm in diameter. In scanning electron microscopy, ~200-nm spheroidal particles were also observed dispersed among the fractal aggregates. The 200-nm spherical particles were composed of metal phosphates. Airborne release fractions (ARFs) were characterized by leaching filter deposits and quantifying metal concentrations with mass spectrometry. The average mass-based ARF for 238U experiments was 1.0 × 10−3 with a standard deviation of 7.5 × 10−4. For the original experiments, DOE-HDBK-3010-94 states, “Uranium ARFs range from 2 × 10−4 to 3 × 10−3, an uncertainty of approximately an order of magnitude.” Thus, current measurements were consistent with DOE-HDBK-3010-94 values. ARF values for lutetium and ytterbium were approximately one to two orders of magnitude lower than 238U. Metal nitrate solubility may have varied with elemental composition and temperature, thereby affecting ARF values for uranium surrogates (Yb and Lu). In addition to ARF data, solution boiling temperatures and evaporation rates can also be deduced from experimental data.

Approaches to the Establishment and Justification of the Size of Emergency Planning Areas around NPPs

Emergency planning zones around facilities that use radiation and nuclear technologies are set up in order to prevent or minimize deterministic effects and reduce risks of stochastic effects of radiation exposure in case of nuclear or radiological emergency. In international practice, in order to enhance effectiveness of response to emergencies, it is common to set up emergency planning zones for nuclear facilities in accordance with their level of threat for the environment and public. As the establishment of such zones requires certain material resources, the size of the zones is to be justified.
 As of today, sanitary-protective zone and monitoring zone in Ukraine could be considered, to a certain extent, as analogues of such emergency planning zones. However, the main functional load of these zones are relevant more for routine operation of nuclear facilities than for the issues of emergency planning and do not have such a specific for the emergency planning zones functions as ensuring necessary infrastructure for conducting such urgent protective actions as evacuation, sheltering, notification, relocation and others in case of severe accidents at NPPs.
 Absence of transparent numerical criteria for determining the size of emergency planning areas, on one hand, and necessity to determine such areas as required by the key IAEA publication GSR Part 7, as well as due to understanding the importance of emergency planning areas in the state emergency response system, on the other hand, make the task on establishing approaches to the definition of the scope of emergency release, which is a framework for emergency zoning, crucial.
 The paper proposes to discuss two approaches to defining the scope of the boundary release, according to which the size of the emergency planning areas is to be defined. The paper presents results of assessing the size of the emergency planning areas around NPPs based on the scope and radionuclide composition of the boundary release.

Carbon nanomaterials based on plant biopolymers as radionuclides sorbent

The technogenic human activities associated with the operation of nuclear power facilities lead to the contamination of natural water bodies and soils with radioactive substances, including heavy radionuclides, such as uranium and thorium. Purification of natural water bodies is a pressing environmental issue. A study of the adsorption capacity for heavy U238 and Th232 radionuclides by the samples of new carbon nanomaterials was conducted. Nanocarbon materials was synthesized based on vegetal polymers, such as technical lignin, starch and from lignocellulosic material—the bark. It was established that the investigated samples have different sorption indices in relation to radionuclides, which is determined by their chemical composition, as well as by the surface-capillary properties of carbonized materials. It is shown that the content of mobile and fixed forms of radionuclides on the investigated sorbents are significantly different. High sorption capacity of the carbonated lignin sample with respect to uranium are shown. A sample of nanocarbon materials synthesized based on the lignocellulosic complex of the bark exhibits high sorption properties in relation to thorium. The possibility of using the carbonic nanomaterial as the sorbents of radionuclides is shown.

Determination of internal and external hazard index of natural radioactivity in well water samples

Well water is an environmental component that is always used by people but is vulnerable to contaminated. The impact of the contamination of water bodies could cause danger to human health. Water pollution could be caused by radioactivity that exceeds recommended limits. Source of radionuclide pollutants in water bodies could be caused by the operation of nuclear facilities. Analysis of radioactivity has been carried out on several samples of well water near the TRIGA 2000 reactor facility, followed by calculating the internal and external hazard index of radiation dose. The results of the analysis using a gamma spectrometer show that the radionuclides contained in well water samples are not fission products, but they are Ra-226, Bi-214, Pb-214 and K-40 in the form of natural radionuclides. The highest radioactivity in the sample was 5.808 Bq/L from K-40 and the lowest was 0.103 Bq/L from Bi-214. The internal and external hazard index has been determined where the internal hazard index was 0.013-0.023 while the external hazard index was 0.006-0.012 which is below the maximum hazard index value based on UNSCEAR which is ⩽ 1. So, based on the results of this study on the radioactivity parameters show that well water is still safe to be used.

Islamism as Threat Factor to Construction and Operation Safety of Nuclear Power Facilities

The paper discusses the hazards of construction and operation of nuclear power facilities in Islamic countries or countries with a predominantly Muslim population that is ambiguous about the development of the nuclear industry in their countries. The analysis shows the issue from the point of view of traditional societies and from the position of the leading countries of the world atomic energy and allows us to highlight the most significant and specific features of the stated problem. The analysis shows the issue from the point of view of traditional societies and from the position of the leading countries of the world nuclear energy and allows us to highlight the most significant and specific features of the stated problem. The conclusion is made about the situational and personal nature of the Muslim community life organization and the dominant role of the authoritative religious and community leaders’ personal opinion in solving issues not related to spiritual life. Leaders in the field of nuclear energy have to discern into the essence of the signs, reasons and development directions of religious factors in these states, and as the Islamic world is a significant geopolitical factor in the entire system of international relations, its interests and Islamist position cannot but take into account the world political forces promoting nuclear power.

Türkiye’de Nükleer Siber Emniyet ve Nükleer Güvenlik

Siber kavramı son on yılda ülkemiz kurumsal hayatına olumlu ve olumsuz yönleriyle birlikte hızlı ve etkin bir şekilde giriş yapmıştır. Nükleer alanda da hızlı girişim ve gelişmeler yaşamakta olan ülkemizde nükleer siber emniyetin sağlanabilmesi önemlidir. Siber alanda ve nükleer alanda yeterliliğe sahip uzmanların hem düzenleyici ve denetleyici kuruluşlarda hem de nükleer tesis işletmecisi kuruluşlar bünyesinde bulunması gereklidir. Nükleer siber emniyetin sağlanması sürecinde yapılacak hataların yaratacağı kalıcı hasar riski, ülkelere bu alanda emekleme süreci yaşama fırsatı tanımamaktadır. Bu sebeple nükleer tesis kurmayı/işletmeyi hedefleyen ülkemizde nükleer siber emniyetle yaşamanın öğrenilmesi, bu alanın risklerini değerlendirme ve vakit kaybetmeden olası risklere yönelik önlemlerin alınması gerekmektedir.

Prevention and control on urban NIMBY caused by nuclear facilities in China

In order to improve the energy structure and the air quality, China has made every effort to develop civil nuclear industry and establish some nuclear facilities. Due to the potential radioactivity of nuclear facilities, the location and construction of the facilities will cause dissatisfaction and panic of the surrounding residents, resulting in “Not in My Backyard (NIMBY)” incidents. This paper will analyze the reasons for the NIMBY incidents, which are inadequate and not timely disclosure of information for residents, the lack of relevant education and compensation mechanism with legal analytical methods. Therefore, the prevention and control methods of such NIMBY incidents should be put forward: Governmental departments and operators of nuclear facilities should adhere to scientific and democratic decision of location selection and construction, and establish proper compensation mechanism for the residents nearby.

Providing support to operators for monitoring safety functions using reinforcement learning

Continuous monitoring and diagnosis are important for safe operation of nuclear facilities. In an emergency shutdown, the diagnostic tasks can be challenging for human operators who may be under intense stress and/or lack training. In recent years, studies using artificial-intelligence technologies have been actively conducted to help in diagnostic tasks. The current study proposes a data-driven approach that leverages deep reinforcement-learning techniques to intelligently learn effective strategies for state diagnosis of safety functions. First, a learning framework and key elements of reinforcement learning are designed as basic components. Then, a deep neural-network structure and a deep reinforcement algorithm are presented for diagnosis learning. The experimental results demonstrate the feasibility of deep reinforcement learning on diagnosing the safety functions of a nuclear facility.

Advances in Nuclear Radiation Sensing: Enabling 3-D Gamma-Ray Vision

The enormous advances in sensing and data processing technologies in combination with recent developments in nuclear radiation detection and imaging enable unprecedented and “smarter” ways to detect, map, and visualize nuclear radiation. The recently developed concept of three-dimensional (3-D) Scene-data fusion allows us now to “see” nuclear radiation in three dimensions, in real time, and specific to radionuclides. It is based on a multi-sensor instrument that is able to map a local scene and to fuse the scene data with nuclear radiation data in 3-D while the instrument is freely moving through the scene. This new concept is agnostic of the deployment platform and the specific radiation detection or imaging modality. We have demonstrated this 3-D Scene-data fusion concept in a range of configurations in locations, such as the Fukushima Prefecture in Japan or Chernobyl in Ukraine on unmanned and manned aerial and ground-based platforms. It provides new means in the detection, mapping, and visualization of radiological and nuclear materials relevant for the safe and secure operation of nuclear and radiological facilities or in the response to accidental or intentional releases of radioactive materials where a timely, accurate, and effective assessment is critical. In addition, the ability to visualize nuclear radiation in 3-D and in real time provides new means in the communication with public and facilitates to overcome one of the major public concerns of not being able to “see” nuclear radiation.

Investigation on the gamma sources integrity inside a dry pit storage

One of the primary concerns in the operation of nuclear related facilities is the safety of the system. Worldwide publicity on a few nuclear accidents as well as the notorious Hiroshima and Nagasaki bombing have always brought about public fear on anything related to nuclear. Thus, investigation and analysis on the safety system shall be continuously conducted to determine the safety condition of the facilities. In the early days, analytical and experimental methods were employed. However, this approach is limited to low risk experimentation. With the advancement of computer technology, specific computer codes were used to predict and analyse high risk safety issues such as the fall-out from a nuclear explosion or analysis of melt down occurrence in a reactor core. This paper discusses a prediction model on a gamma irradiation facility source pit which having failure on its air cooling system. The CFD model predicts the temperature of the gamma sources under such situation to determine its integrity.

A practical challenge-response authentication mechanism for a Programmable Logic Controller control system with one-time password in nuclear power plants

Abstract Instrumentation and Control (I&C) systems of nuclear power plants (NPPs) have been continuously digitalized. These systems have a critical role in the operation of nuclear facilities by functioning as the brain of NPPs. In recent years, as cyber security threats to NPP systems have increased, regulatory and policy-related organizations around the world, including the International Atomic Energy Agency (IAEA), Nuclear Regulatory Commission (NRC) and Korea Institute of Nuclear Nonproliferation and Control (KINAC), have emphasized the importance of nuclear cyber security by publishing cyber security guidelines and recommending cyber security requirements for NPP facilities. As described in NRC Regulatory Guide (Reg) 5.71 and KINAC RS015, challenge response authentication should be applied to the critical digital I&C system of NPPs to satisfy the cyber security requirements. There have been no cases in which the most robust response authentication technology like challenge response has been developed and applied to nuclear I&C systems. This paper presents a challenge response authentication mechanism for a Programmable Logic Controller (PLC) system used as a control system in the safety system of the Advanced Power Reactor (APR) 1400 NPP.

Experimental Runaway Electron Current Estimation in COMPASS Tokamak

Runaway electrons present a potential threat to the safe operation of future nuclear fusion large facilities based on the tokamak principle (e.g., ITER). The article presents an implementation of runaway electron current estimations at COMPASS tokamak. The method uses a theoretical method developed by Fujita et al., with the difference in using experimental measurements from EFIT and Thomson scattering. The procedure was explained on the COMPASS discharge number 7298, which has a significant runaway electron population. Here, it was found that at least 4 kA of the plasma current is driven by the runaway electrons. Next, the method aws used on the set of plasma discharges with the variable electron plasma density. The difference in the plasma current was explained by runaway electrons, and their current was estimated using the aforementioned method. The experimental results are compared with the theory and simulation. The comparison presented some disagreements, showing the possible direction for the code development. Additional application on runaway electron energy limit is also addressed.

Nuclear Security Related Attributes and Characteristics of Different Types of Nuclear Facilities

Existing International Atomic Energy Agency (IAEA) Nuclear Security Series (NSS) publications do not provide specific guidance for different type of nuclear facilities; these are typically meant as general guidance for nuclear facilities rather than having specific application to any specific facility type. Accordingly, the question may rise whether operators of different nuclear facilities would need to take account of the specific characteristics of their facilities during the implementation of the recommendations and guidance provided in IAEA NSS publications. The comprehensive answer to the question (regarding each type of nuclear facilities) requires the identification of the above mentioned specific characteristics of all nuclear facility types and the systematic assessment of the exiting IAEA NSS publications, including IAEA Nuclear Security Series No. 13 and other implementing and technical guides. The identification of specific characteristics of different nuclear facilities that may influence the design and implementation their physical protection systems and measures is the starting point of this comprehensive review process.

Economic efficiency of the nuclear power industry and social aspects of its development

The article attempts to develop a system of parameters for an objective and comprehensive assessment of the efficiency of the nuclear power industry in terms of its contribution to the country’s economic and social development, as well as its environmental well-being and its geopolitical position. Currently, nuclear power industry makes up a significant part of the energy supplies in the developed countries throughout the world. However, in the developing economies, including those of East and Southeast Asia, it plays a less prominent role. Nevertheless, in recent years, China has been the leader in commissioning new atomic facilities, thanks to the consistent implementation of its state program for the development of the nuclear power industry. Forecasts indicate that in the near future, the share of atomic energy will remain stable and account for about 10 % of all global energy capacity, which is confirmed by the estimates made during the study. However, in the long term nuclear energy cannot be ignored as an economically efficient and environmentally friendly source of energy, as well as a factor in improving the quality of life of the population when developing a strategy for the sustainable development of a country. The article examines the already existing assessment criteria for the economic efficiency of nuclear power plants (NPPs), and proposes new standards for the assessment of its contribution to the development of the community and a country’s stance on the global political stage. The article also identifies the main obstacles to the further development of the industry in the modern world. The research showed that the main specific feature of an NPP operation from the economic point of view is extremely high initial construction and commissioning costs, with relatively low further operation costs, which determines long payback lines and liquidity shortages reducing the attractiveness of such projects for potential investors. These peculiarities determine the leading role of state authorities in the launch, operation and modernization of nuclear power facilities.

Estimation of occupational compensation based on a linear-quadratic methodology for the nuclear industry

Production of nuclear electricity is under scrutiny because of health issues connected with operation of nuclear facilities. National and international regulatory institutions aim to have regulations that ensure that any radiation dose received by the workers are kept as minimal as possible to reduce any risk on human health. Under these circumstances when a controlled nuclear facility is operating in standard conditions the possibility to have direct injuries connected by non-stochastic effects of ionizing radiation will happen only if regulations are violated. In addition, the stochastic effect of radiation may cause cancer. Nuclear power plants calculate the cost of potential health damage caused by ionizing radiation based on the Linear No-Threshold Relationship (LNT) between the dose and cancer risk. However, recent radiological research questions the validity of the LNT relationship for low and very low doses. In this paper, a new methodology based on a linear-quadratic function is proposed for the cost estimation of health risks induced by ionizing radiation, this new methodology results in significantly higher monetary cost for higher doses. At the same time the new methodology also results in lower monetary cost for low exposure levels and even zeros payment for environmental doses because they cannot be avoided. By adopting this new methodology it could provide motivation for nuclear facilities to improve health & safety measures.

Intellectual decision-making system in the context of potentially dangerous nuclear power facilities

The article deals with intelligent operation decision support system under condition of potentially hazardous nuclear facilities. The proposed system is referred to the class of advising systems and does not make final decisions in case of deviations of parameters to be analyzed, but generates general ways to solve an encountered problem and issues a set of recommendations for the plant personnel. In the article a fuzzy logic tool is used as mathematic tool. Lessons learnt from operation of nuclear facilities demonstrate that existing critical components (parts, areas, welding joints) are subject to increased failure under conditions of high operational loads, including beyond design loads and negative environmental impact. Usually in that situation there is probability of equipment integrity failure, when the unit is at power, with severe defect downing. For instance, the coolant leak and potential development of initial penetration defect to critical dimensions. In other words, in fact, the final observable result is always one – formation and development of operational crack which jeopardizes design integrity of the component and, accordingly, seriously compromises the nuclear power unit operation. The proposed situational model is linked with real knowledge data base where generated situational pairs are stored. The expert system is used for knowledge data base formation. Actually the proposed system consists of two independent fuzzy systems. From mathematical tool point of view, the advantage of such systems combination is lack of defuzzification unit in the first system and fuzzification unit in the second one.