The Need for Integrated Cybersecurity and Safety Training

The role of the reactor size for an investment in the nuclear sector: An evaluation of not-financial parameters

Reducing neutron activation to support early dismantling of light water reactors

In recent years, Rosatom has dominated the world nuclear energy market. This Russian state-owned company has around 36 portfolios of new nuclear power plants (NPP) in various countries. In addition, Rosatom also controls about 17% of the nuclear fuel market. This research aims to find out how Rosatom can dominate the global nuclear energy market. To answer that, this study used a qualitative descriptive research method with the neomerkantilism concept approach. The data collection technique is done by means of literature study or literature study. The results of this study indicate that Rosatom can dominate the global nuclear energy market due to the influence and support of the Russian state. Russia made Rosatom a state-owned company aimed at pursuing maximum revenue through exports of nuclear energy for the sake of increasing the national economy as well as its global political influence.

Working in nuclear cycle facilities such as nuclear power plants, fuel mining, milling and fabrication, waste management, and reprocessing facilities can pose various industrial health and safety risks to the workers due to hazardous processes and materials. Conventional or non (ionizing) radiation-related occupational health and safety (OHS) in nuclear facilities is a multidimensional area that involves hazard identification, protective measures, safety culture, emergency response, and workers’ well-being. This article aims to highlight the International Atomic Energy Agency’s perspective of OHS, the common conventional OHS hazards in nuclear cycle facilities, and the measures taken to mitigate risks from these hazards. By implementing comprehensive OHS management system, nuclear facilities can create an occupationally healthy and safe working environment.

Modeling and assessment of human and organization factors of nuclear safety culture in Saudi Arabia

Development of a quantitative resilience model for nuclear power plants

Enhancing equipment qualification testing facility for nuclear power plants: Achieving rapid temperature and pressure increase during design basis events

The criteria and requirements for consideration of rare tectonic and seismic events at the locations of nuclear power plants (NPP) were subject to comparative analysis in the context of the aftermath of the earthquake with M w = 8.9 that happened on March 11, 2011 in the southeast of Honshu Island. The main problems of regional and detailed methods for seismic hazard assessment under selection of safe placement of nuclear plants are discussed. Deterministic and probabilistic estimates of the parameters of seismic impacts on the Fukushima-1 NPP were considered taking into account the consequences of the March 11, 2011 earthquake. The development of the uniform requirements to safe placement of nuclear power stations and unified methods for seismic hazard assessment is proven to be urgent. It is necessary to take into account the possible causes of extreme seismic events able to result in the beyond design-basis accidents not considered in the project and also organizational and technical measures to reduce the radiological consequences of the beyond design-basis accidents caused by the impact of rare but severe natural and anthropogenic factors.

Historically, the role of professionals specialized in occupational health and safety (OHS) has emerged from the need to protect employers working in major risk industries such as nuclear plants and large-scale chemical industries in Europe. More recently, a few studies highlighted that the range of activities linked to safety management responsibilities includes monitor and prepare reports, inspection and auditing, regulatory compliance, emergency response, incident investigation, hazard and risk assessment, and training. Additionally, there are some supplementary non-safety related duties, such as including environmental responsibility. Considering that work-related musculoskeletal disorders (WRMD) are a major burden worldwide, adding up to 1.3 billion cases, more than 100 million years loss of disability-adjusted life years and that such disorders are common causes of disability and sick leave, this topic is highly relevant to OHS professionals. In EU Member States for which data are available, a large majority of all workers report complaints related to musculoskeletal disorders as their most serious work-related health problems. The percentage of workers reporting such complaints as their most serious health problem ranges from 40 % in Luxembourg to 70 % in Czech Republic and Finland. Furthermore, more than half of workers with musculoskeletal disorders reported taking time off work in a 12-month period. In the EU, 26 % of workers with musculoskeletal long-lasting disorders, that is lasting over 3 months, combined with other health problems report more than 8 days of absence per year. Higher Education Institutions (HEI) have a key role in disseminating and increasing accessibility to the most up-to-date evidence available regarding the impact and management of musculoskeletal disorders, to facilitate translation of knowledge to implementation in practice. This way, the Knowledge Alliance Prevent4Work for Preventing Work-Related Musculoskeletal Disorders has elaborated this document with the most recent and relevant knowledge within the topic. HEI that offer courses within OHS as well as graduation and post-graduation courses for health professionals that work within the area, may benefit from the recommendations presented here.

After the Japanese Fukushima-Daiichi accident, the extreme event beyond the design basis accident is realized to be possible in the combined disasters. The current mitigation strategy of ECCS could fail because the low pressure injection system with electrical pumps will fail in a station blackout accident. To utilize the best of residual steam by the turbine driven pump is a possible alternate mitigation strategy and is analyzed in the paper. An advanced safety analysis tool with fast, accurate and integrated man-machine interface is necessary to analyze more different cases in the extreme accident and provide more safety precautions and more operation strategies for the plant owners. The TRACE code, the latest and advanced best-estimate simulation code, incorporates the four important codes, TRAC-P、TRAC-B、RELAP5 and RAMONA, and a graphic user interface, Symbolic Nuclear Analysis Package (SNAP), to provide a modern thermal-hydraulic analysis tool with fast and integrated inputs, and will become the NRC’s flagship thermal-hydraulic analysis tool in the near future. The TRACE model of Chinshan nuclear power plant with the same BWR/4 reactor of Fukushima-Daiichi NPP is developed, (1) based on the plant design data; (2) consists of different modules to simulate the reactor systems; and (3) analyzes the 3D thermal-hydraulic phenomena through the 3D VESSEL component and more practical thermal-hydraulic phenomena can be analyzed in the downcomer, fuel-assembly reactor core, core bypass, and upper and lower plenum. The Chinshan TRACE model, which has been benchmarked through several transient cases with the Chinshan FSAR report, the start-up data and the transient results of RETRAN data, can be adopted for analyzing both hypothetical transient scenarios and loss-of-coolant accidents, and further more for the alternate mitigation strategies of the extreme accidents of Fukushima-Daiichi type. In this paper, a double-ended guillotine (DEG) break on the recirculation loop is analysis. The Fukushima-Daiichi type accidents, the extended station blackout (SBO) accidents, are evaluated with several scenarios like no break, one SRV stuck open and the various break areas with the 1%, 10%, 100% cross areas of recirculation loop. The current RCIC injection flow rate is not sufficient in a very small break like 1% break area of a recirculation loop and even in the stuck open of a safety/ relieve valve (SRV). The reactor water level will sharply reduce when the reactor pressure is released and result in a fast increase of the fuel temperature. In this situation, the reactor pressure will increase once the coolant being injected that will reduce the effect of the external low pressure injecting system. Thus, the turbine driven pumps, the RCIC pump and the HPCI pump, are one of the important alternate mitigation strategies in the extended SBO. Through this paper, the more advanced analysis on the combined accidents could be performed for the improvement of nuclear safety.

As the brain of Nuclear Power Plant (NPP), Main Control Room (MCR) is an integrated system which comprises varieties of Human System Interfaces (HSIs), procedures, operators and environment. HSI is the medium that the operators monitor and control the Nuclear Power Plant. To improve the operating performance and avoid human errors, Human Factor Engineering (HFE) is required to be implemented in the new plant HSI design for plant safety. HPR1000 has followed the NUREG-0711 as the guidelines of HFE program, in which 12 elements are included. Task Analysis (TA) and Human Factor Verification & Validation (HF V&V) are two important elements for the HSI design. For task analysis, the design engineers could analyze the human actions (HAs) to identify the tasks that the operators must perform to accomplish the plant functions. Task analysis identifies not only the specific tasks needed to accomplish HAs but also the information, and controls required to complete those tasks which are considered as important input for the MCR HSI design. HF V&V is one of the final stages of the Human Factors Services as included in NUREG-0711. The HF V&V objective is to evaluate that the HSI design conforms to HFE design principles and that the adequacy of the interfaces enable plant personnel to successfully perform their tasks and other operational goals, assuring plant safety. The V&V element consists of four major activities: Sampling of Operational Conditions, Design Verification, Integrated System Validation, and HED Resolution. For different targets, Design Verification could be separated into two kinds of activities: HSI Task Support Verification (TSV) and HFE Design Verification (DV). TSV is an evaluation to verify that the HSI supports the requirements of personnel tasks, as defined by task analyses. The HAs, controls and information identified in task analysis could be used as the basic input for HSI TSV. To provide adequate input for the HSI design and TSV, the operational conditions of task analysis should be sampled as many as possible to cover all the typical conditions, which include normal conditions, transients, Design Based Accidents (DBA), Beyond Design Based accidents (BDBA), even severe accidents. The sampled conditions for task analysis would be available for the task support verification of the related HSIs. In conclusion, the task analysis could be used as the design input for HSI, while the task support verification could review the designed HSI with the output information from TA. This paper addresses the research and engineering implementation methodologies for task analysis and HSI task support verification. As the first reactor of HPR1000, HFE program have been carried out in Fuqing 5&6 MCR from preliminary design to final test. The Fuqing 5&6 TA and TSV achievements for MCR HSIs design are summarized in the paper.

The value of modern decision-making support services to fusion projects

Problem statement. In connection with the conduct of hostilities in the territory of the Dnipropetrovsk region and in other territories of Ukraine, the enterprises of the nuclear fuel complex are constantly faced with environmental dangers that can bring shelling and bombing. Along with this, there is the possibility of carrying out terrorist acts at radiation-hazardous facilities or at energy facilities of Ukraine. In connection with the fact that the industrial sites of the former uranium production of the “PCH” industrial complex are located quite close to the line of combat, this leads to an increase in the dangers and risks of an environmental accident with the release of radioactive substances. The purpose of the article is to analyze the existing regulatory and legal acts that ensure stable regulatory, organizational and technological functioning of such radiation-hazardous facilities as industrial sites and separate tailings storage facilities (sludge impoundments) using the example of the former uranium production of the "PCH" industrial complex. Determine the possibility of regulatory and legal application of express methods of registration of radiation pollution by the method of remote data collection and mathematical modeling in radiation-contaminated territories, if there is a man-made or military emergency. Conclusion. During the analysis of threats to radiation-hazardous objects located in the Dnipropetrovsk region, it was determined that the main threat is man-made industrial or military accidents at RНO with the release of radioactive substances into the atmosphere, lithosphere and hydrosphere. Since the beginning of the full-scale war of the Russian Federation against Ukraine, the enemy has captured two nuclear plants: the Chornobyl nuclear power plant in the Kyiv region and the Zaporizhia nuclear power plant in the Zaporizhia region. That is why it is necessary to determine what actions need to be taken in order to fulfill the requirements of regulatory and legal documents and acts of the state in the conditions of constant threats and dangers in the conditions of military aggression. In accordance with the actions, it is also necessary to determine and calculate the environmental consequences of a possible man-made accident or military shelling in the conditions of an operating enterprise that performs security, physical protection and radiation monitoring of the RНO.

This document is aimed at providing guidance to the National Nuclear Security Administration?s (NNSA) Office of International Nuclear Security?s (INS) country and regional teams for implementing effective physical protection systems (PPSs) for nuclear power plants (NPPs) to prevent the radiological consequences of sabotage. This recommendation document includes input from the Physical Protection Functional Team (PPFT), the Response Functional Team (RFT), and the Sabotage Functional Team (SFT) under INS. Specifically, this document provides insights into increasing and sustaining physical protection capabilities at INS partner countries? NPP sites. Nuclear power plants should consider that the intent of this document is to provide a historical context as well as technologies and methodologies that may be applied to improve physical protection capabilities. It also refers to relevant guidance from the International Atomic Energy Agency (IAEA) and the U.S. Nuclear Regulatory Commission (NRC). This document includes insights, lessons learned, and guidance from nuclear security subject matter experts (SMEs) experienced in developing, implementing, and sustaining PPSs at operating commercial NPPs.

Security research and training is attracting a lot of investment and interest from governments and the private sector. Most efforts have focused on physical security, while cyber security or digital security has been given less importance. With recent high-profile attacks it has become clear that training in cyber security is needed. Serious Games have the capability to be effective tools for public engagement and behavioural change and role play games, are already used by security professionals. Thus cyber security seems especially well-suited to Serious Games. This paper investigates whether games can be effective cyber security training tools. The study is conducted by means of a structured literature review supplemented with a general web search.While there are early positive indications there is not yet enough evidence to draw any definite conclusions. There is a clear gap in target audience with almost all products and studies targeting the general public and very little attention given to IT professionals and managers. The products and studies also mostly work over a short period, while it is known that short-term interventions are not particularly effective at affecting behavioural change.