International Conference on
Nuclear Energy
Scientific Program
Keynote Session:
Title: When in the life cycle of a Nuclear Power Plant does Nuclear Safety Culture become important? Nuclear Safety Culture……. What is it? An unnecessary expense in the early stages of Nuclear Construction Projects?
Biography:
Phillip Harris trained in the UK as a Draughtsman, worked in Germany as a welding inspector and joined the UK nuclear industry in 1978. He worked as a Mechanical and Operational Engineer on Magnox and Advanced Gas Cooled Reactor plants. In 2000 he joined the training team at Hinkley Point B where Human Performance and Nuclear Safety Culture became his passion. He believes that the principles of Human and Organizational Performance (often referred to as HOP) form the foundation for a strong Nuclear Safety Culture. More recently he has been working with the Hinkley Point C Supply Chain and as Senior Nuclear Safety Culture Specialist at Barakah Nuclear Power Plants here in the UAE.
Abstract:
What is required to create a strong Nuclear Safety Culture? Surely it’s not too difficult! If you train people to do their job and your leadership re-enforce your messages strongly enough, what can go wrong? We may need to implement an observation process to ensure that they always demonstrate the right behaviors. Wrong! Trying to fix the workers will not create a strong Nuclear Safety Culture.
Whether you are the Joint Venture partners or a Tier 3 Supplier in the Nuclear Supply Chain your people are not a part of the problem, they are the solution to creating a strong Nuclear Safety Culture by;
- Recognizing that as humans we make mistakes.
- Management allowing your people to work in an environment where it is accepted as necessary for them to challenge and question to identify your system and Organizational weaknesses[i] to enable resilience to be created within your organization.
The IAEA, WANO and INPO all advocate the need for a Nuclear Safety Culture to be nurtured within all the projects individual contributors. They need to understand that Nuclear is different, it is special, and the required standards are higher. Maintaining ‘Defense in Depth’ is essential when dealing with complex technologies[ii].
Yes, it is often seen as an unnecessary expense but failure to create a strong Nuclear Safety Culture is often costlier as defense in depth is not maintained.
Title: KIT Numerical and Experimental Investigations for LWR Reactor Safety
Biography:
Victor Hugo Sanchez-Espinoza is nuclear engineer with long experience in safety-related investigations for Gen-II, III Light Water Reactors including SMR. He is head of the Group "Reactor Physic and Dynamics" at KIT CN and lecturer at the KIT Campus South on Reactor Safety Fundamentals and Safety Assessment of NPPs. More than 20 years of experience on core neutronics, thermal hydraulics and safety analysis methodologies for research reactors and nuclear power plants of Gen-II, III and IV. Main areas of interest are validation of multi-scale and multi-physics codes, reactor dynamics, coupled Neutronic/Thermal hydraulics and uncertainty quantifications. Dr. V. Sanchez is WP Leader of the EU CESAM Project and of the German WASA-BOSS Subproject F, both devoted to the improvement of SAMG for LWR using the codes such as ASTEC and ATHLET-CD. He is acting as IAEA expert and he took part in different IAEA missions devoted to severe accident assessment of BWR. Email
Abstract:
Nuclear power plants are complex systems where different phenomena is taking place e.g. neutron-matter interaction within the core, single and two phase flow and heat transfer within the primary and secondary circuits. The safety evaluation of nuclear power plants requires both validated numerical simulation tools –called safety analysis codes- and experiments dedicated to key-safety relevant phenomena. The NUSAFE Research Program of the Karlsruhe Institute of Technology (KIT) is engaged since many decades in both experimental and numerical investigations for both design basis accidents and severe accidents of LWR. As part of the research strategy, the analytical word is devoted to the development of computer codes (TWOPORFLOW, SUBCHANFLOW), its verification, validation, and uncertainty quantification. In parallel keyexperiments are performed for example in the WENKA or COSMOS facilities. The numerical investigations for the assessment of design basis accidents is following the multiscale and multi-physics approach. In this context, the coupling of different codes/solvers (neutronic, thermal hydraulic and thermo-mechanics) outside and within the European Reactor Simulation Platform (NURESIM), which is based on the open source software SALOME, is being extended and improved within European or national research initiatives. For example, the in-house code SUBCHANFLOW was implemented in the NURESIM-Platform and coupled with core simulators such as DYN3D and COBAYA3. In addition, SUBCHANFLOW is coupled with the simplified transport DYN3D-SP3 solver for high fidelity core simulations at pinlevel taking into account local feedbacks. Since data at pin level is very scarce, the development of high-fidelity coupled simulations based on Monte Carlo methods and subchannel codes are pursued for code validation. At KIT, MC-codes MCNP5 and SERPENT were coupled with SUBCHANFLOW code. These methods make possible the simulation of whole PWR cores at pin level, e.g. the PWR UOX/MOX. Finally, Fukushima accident underlined the needs for the further development and improvement of severe accident simulations tools. At KIT a set of key experiments to address in- and ex-vessel phenomena in LWR (QUENCH, LIVE, DISCO, MOCKA) were built and the data generated is used for code validation e.g. of ASTEC, ATHLETCD, MELCOR, etc. This presentation will present and discuss the KIT approach followed to improve the prediction accuracy of safety analysis tools. Selected examples will be given for the validation of codes and the new capabilities under development of advanced simulation tools.
Oral Session 1:
- Fundamentals of Nuclear Engineering | Nuclear Fission | Nuclear Fusion | Nuclear Reactors | Nuclear Law
Title: Management Bodies: Management in Nuclear Energy Field
Biography:
Andranik Hakobyan, currently a Senior State Inspector at the Armenian Nuclear Regulatory Authority, has 14 years of experience in Nuclear Safety, having worked on complex projects in the nuclear energy sector, both domestic and international, and become familiar with International Atomic Energy Agency systems and guidelines. Over his 14-year career, Hakobyan has developed extensive experience in regulations-drafting, regulatory inspections, licensing, NPP life extension regulatory evaluation, and risk management evaluation, among other skills. With a result-driven attitude, an ability to work constructively and as a member of team, negotiation skills honed throughout his career and the attention to detail necessary of a nuclear regulator, Hakobyan’s years of experience coupled with his work ethic make him an asset to any team.
Abstract:
In the context of growing energy demands to fuel economic growth and development, climate change concerns and price volatility of fossil fuels, and in consideration of substantially improved safety and performance records of nuclear power plants, some 60 countries have expressed interest in considering, actively planning or expanding nuclear power.
As recent experience in construction shows, there is a list of challenges, such as construction schedules of nuclear power plants, the complexity of the vendor-customer relationship, length of the supply chain, the globalization of the nuclear industry, and, of course, safety culture.
it is recognized that the lack of proper project management skills is one of the major factors that has been attributed to the safety of nuclear power plants as well as licensing requirements, public intervention, suppliers, and funding problems.
Nuclear accidents have been perceived and considered as global issues since they have worldwide implications on agriculture, land use, fishery, tourism, transport, and trade. Therefore, lessons learned are taken into consideration by NPP design and research organizations and by the managers in all phases of a new nuclear power development program from the regulatory requirements to the site selection phase, pre-construction and licensing phase, and to all successive project implementation phases, including construction, commissioning, and operations.
Management in the nuclear energy field is an integrating activity and its description requires first an understanding of associated functions such as engineering, quality assurance, procurement, and accounting. It comprises leadership functions primarily concerned with the organization, coordination, and control of large human, equipment, and material undertakings with the aim of achieving technical excellence by working to quality standards, optimizing the schedule, the supply chain and minimizing costs. Competent project management can reduce costs through more efficient work sequences, higher productivity shorter activity durations, and the parallel reduction of accumulated interest during construction.
Title: Thermal Hydraulic Analysis of Supercritical Water Reactor Cooled by TiO2 Nano Fluid
Biography:
I have a good experience in the field of design for hydraulic and thermal hydraulic projects. I participated in the design of pipelines for central air conditioning projects. I have good academic and technical experience in the field of ventilation and central air conditioning. Good experience in the fire fighting systems and plumbing design .Mechanical design, selection and installations of “Pumps, Valves, and all fittings” for many usage. Calculation, Selection, Installation of a cooling towers piping, fans, its pump station, and its conventional instrumentation. Calculation, Selection, Erection and maintenance of heat exchangers of different types. Design and supervision of installation of Fire system. Good background about the design standards and procedures, also design system and Tools.
Abstract:
Heat transfer study of nanofluids as coolant in SCWRs core has been performed at Helwan University. A thermal hydraulic code has been produced to study the effect of TiO2 nanofluid water based as a coolant with comparison with pure water as a coolant. Various volume fractions of nanoparticles TiO2 (2%, 6% and 10%) were used in order to investigate its effects on reactor thermal–hydraulic characteristics. Based on Parameters of a SCW Canadian Deuterium Uranium nuclear reactor (CANDU), the fuel assembly was modeled to study the effect of nanoparticles volume fraction on thermos-physical properties of basic fluid and the temperature distribution of fuel, cladding surface and coolant in axial direction. The theoretical results showed that the density, viscosity and thermal conductivity of the coolant increases with the increase of nanoparticles volume fraction. Contrasting to specific heat, which decreases with the increase in nanoparticles volume fraction. Thermal conductivity increases with 2%, 6% and 10% volume fraction of nanoparticles by 5.5 %, 18.1%, 32.1% respectivly, at constant pressure 25 (MPa). For 10% volume percentage of nanoparticles the coolant temperature difference with pure water is about 24.2 °C , 62.5 °C and 94°C at constant pressure 25, 30, and 35 (MPa) respectivly. On the other hand, using nanofluid with 10% volume percentage of nanoparticles as coolant has significant effect on fuel temperature that the maximum fuel temperature reduced by 26.2%, 23.8% and 18.9% at constant pressure 25, 30, and 35 (MPa) respectivly.
Title: SMR Neutronics and Thermal-Hydraulics Safety-Related Investigation
Biography:
Yousef Alzaben is a PhD student in his last year at Karlsruhe Institute of Technology (KIT). His PhD thesis is devoted to SMR investigation from both neutronics and thermal-hydraulics aspects. Mr. Alzaben prior of joining KIT, he worked as a core neutronics engineer for the design of the 1st Saudi-Arabian research reactor which was carried-out by INVAP company. In addition, he is holding a research associate position at King Abdulaziz City for Science and Technology (KACST).
Abstract:
Worldwide many countries are interested in developing light-water Small Modular Reactors (SMRs) due to its (1) attractive economics which enables standardization, modularization and factory fabrication, (2) taking advantage of the accumulated industrial experience in LWRs, and (3) enhanced safety features through the integral design. SMRs can offer solutions for countries that have locations far away from electrical grids or limited infrastructure. It can also provide solutions for an increased demand for water desalination and district heating.
At Karlsruhe Institute of Technology (KIT), safety-related investigation has started to study the Korean’s soluble-boron operated SMR core concept (SMART) and to modify the core design to operate without soluble-boron in the coolant. Therefore, the details of the fuel assembly design and core arrangement are different from SMART core design. The developed core design is called Karlsruhe Small Modular Reactor (KSMR). The KSMR-core is a boron-free core characterized by enhanced safety features as a result of (1) avoiding concerns related to boric acid induced corrosion of pressure vessels internals, and (2) eliminating the probability of boron dilution accidents. Many proven PWR technologies were adopted in the KSMR core in terms of fuel assembly design and material selection.
The KSMR core was designed to limit and establish sufficient margins to thermal-crisis, cold shutdown margin, and pin peaking factor through the proper design of burnable absorbers and control rods. Utilizing multi-physics coupled tools; KSMR core behavior fulfilled the imposed design and safety objectives. In this presentation, core characteristics from both neutronics and thermal-hydraulics will be demonstrated and discussed along with strength assessment of the KSMR core under control rod ejection accident
Keynote Session:
Title: Decommissioning among the challenges of a new build nuclear project
Biography:
Katia Emilova Slavcheva has her expertise in the nuclear industry since 2003. She worked for the Nuclear Power Plan Kozloduy in Bulgaria. She also contributed to projects providing support to the Nuclear Regulatory Authorities by international teams in Europe, Russia, Ukraine, Armenia, Georgia, Mexico, Philippines and Jordan. Currently she joint the ambitious new build project in UAE. Her fields of expertise are Decommissioning, RWM, Radioactive Sources, Public Acceptance, Training and Capacity Building in the Nuclear
Abstract:
Statement of the Problem: The successful introduction of nuclear power and its safe, secure, peaceful and sustainable application is an issue of central concern, especially for countries that are implementing their first new build nuclear project. In preparing the necessary nuclear infrastructure, the pertinent activities can be split into three progressive phases of development and corresponding milestones. Decommissioning is an integral part of a nuclear power plant life cycle. In the best scenario, it comes after running the plant for 60 years.
The purpose of this study is to explain why it is important to:
- Establish a sound regulatory requirements concerning decommissioning since “ready to commission and operate” phase.
- Prepare an Initial Decommissioning Plan
- Establish a Decommissioning Trust Fund
- Perform an Site Specific Decommissioning Cost Estimate
- Inform all stakeholders
- Identify the Waste Management Organization
Findings: Nuclear industry started after the WWII. In the dawn of the nuclear the main goal was the electricity generation. Attention came on the decommissioning issue only when bigger part of the nuclear power plants all over the world started to be close to their operational lifetime end. That’s how decommissioning came into the focus of the nuclear industry. Conclusion & Significance: Adequate regulatory basis, operator’s responsibility to prepare and update every 3 years an Initial Decommissioning Plan, estimate the future decommissioning costs and start to allocate resources from the electricity price since day one of the production will help us to keep the promise not to burden the future generations.
Title: Mathematical Modeling of Thermal Hydraulic Parameters of Supercritical Water Reactor using Alternative Nuclear Fuels
Biography:
I have a good experience in the field of design for hydraulic and thermal hydraulic projects. I participated in the design of pipelines for central air conditioning projects. I have good academic and technical experience in the field of ventilation and central air conditioning. Good experience in the fire fighting systems and plumbing design .Mechanical design, selection and installations of “Pumps, Valves, and all fittings” for many usage. Calculation, Selection, Installation of a cooling towers piping, fans, its pump station, and its conventional instrumentation. Calculation, Selection, Erection and maintenance of heat exchangers of different types. Design and supervision of installation of Fire system. Good background about the design standards and procedures, also design system and Tools.
Abstract:
), for hot channel and reaches to 795.8), for average channel but the clad temperature reaches to 615.8), for hot channel and reaches to 396.3), for average channel and for the coolant the temperature reaches to 541.4), for hot channel and reaches to 366.6), for average channel. For (UC) fuel at pressure of 26(MPa), the results shows that the max fuel temperature reaches to 1550), for hot channel and reaches to 770.1
), for average channel while the clad temperature reaches to 615.8), for hot channel and reaches to 396.3), for average channel and for the coolant the temperature reaches to 541.4), for hot channel and reached to 366.6), for average channel. For (UC2) at pressure of 26(MPa), the results demonstrate that the max fuel temperature reaches to 1566), for hot channel and reaches to 776.2), for average channel while the clad temperature reaches to 615.8), for hot channel and reaches to 369.3) and the coolant temperature reaches to 541.4), for hot channel and reaches to 366.6), for average channel. Oral Session 1:
- oral presentation
Title: Challenges and Popular acceptance in Nuclear Energy Management in Sudan
Biography:
I am highly motivated, hardworking and passionate individual would like to build an acclaimed academic career based on more than 15 years of research and teaching experience in the field of health and radiation physics aiming to improve and develop technologies of radiation detection and measurements in environmental. In fact, I carry multiple universities degrees (B.Sc. Applied Physics and Math), (L.L. Bachelor of Law), (IAEA Higher Diploma in Radiation Protection and Safety of Radiation Sources) and (M.Sc. in Radiation and Environmental Protection). I am a capable and professional individual who is able to perform to the highest standards in areas such as environment radioactivity, NDT, radiation detection, NORM measurements, dosimetry, gamma spectroscopy, quality control of medical equipment, and research. Besides, I am skillful in planning, knowledge, report writing, and documentation. I’m sound in both oral and written Arabic and English. I have experience in project management professional (PMP) and internal audit.
Abstract:
The establishment of nuclear power plants requires highly technical, industrial, institutional and legal capabilities, especially for newcomers to the club. Developed countries in the field of nuclear energy faced enormous difficulties and challenges in managing their nuclear energy projects, especially when there were accidents or errors, even if they were small. The most prominent examples of these incidents were the famous accident at the Chernobyl nuclear reactor in Ukraine's 1986 and Fukushima Daichi nuclear power in Japan. Therefore, newcomers countries in the nuclear club, like our Arab countries, could raise great concerns within their borders and neighbors countries when it takes serious steps to build nuclear power reactors. Here, the paper raises its central question: how can developing countries plan and implement their nuclear energy projects to meet their energy needs, and that these projects have broad popular acceptance and, most importantly, acceptance A regionally and internationally? Therefore, the international acceptance provides the projects of our Arab countries unlimited opportunities of funding, cooperation, transfer of expertise, training of cadres, developing their industrial capacities in this field and expanding their use of this type of energy to cover all their needs. The paper tries through its three sections; Knowledge Management and Nuclear Energy, And its popular acceptance, to define broad outlines in this regard that could contribute to the development of the first building infrastructure to ensure that nuclear energy projects in the Arab countries are widely popular.
Title: Addressing electrical power supply continuity by enhance the reliability of auxiliary power system to reactor coolant pumps after grid collapse due to natural disaster or man-made threats
Biography:
Hello, Myself Md Shamsul Huda Sohel and have to Completed my graduation in Electrical and Electronics Engineering and post-graduation in Nuclear Engineering. Presently, I works as an Assistant Engineer at Ashuganj Power Station Company limited (APSCL), which is government own largest power station in Bangladesh Under Bangladesh Power Development Board (BPDB). My carrier goal becomes to develop myself on nuclear safety and security sites. Recently, I achieved two success. My two safety & security based paper published in year 2017, one is new idea based focus on safety & security type at International Journal of Nuclear Security (IJNS) and another is safety of RPV crack analysis at Bangladesh Academy of Sciences.
Abstract:
Today’s nuclear power generation is the right example for peaceful use of nuclear energy. Generates electricity through nuclear energy become similar as fossil fuel plant except it’s heat producing method. Reactor core is that device to produce heat through controlled nuclear chain reaction and transfer them by coolant pumps. Since decay heat is sufficient to meltdown reactor core, we must be ensure to serviceable the coolant pumps continuously for overlong period after the chain reaction stopped. So, at this article just focus on long-term uninterrupted power supply to the Reactor Coolant Pumps if, all the incoming and outgoing grid towers are collapse due to natural disaster or intentionally through terrorism threats. Lack of grid supply for long period might be concerning with nuclear safety- security issue, because of towers re-construction is lengthy process and sooth to say mobile generators, UPS, battery back-up are not sufficient for yearly continuous power supply without interruption. To overcome this situation, established a diesel based peak load plant nearby or very closely with NPP and has a double capacity of coolant pumps. This diesel engines are one-tenth in total capacity and assembled them parallel. It’s because, if trouble occurs at individual unit, rest of the engines are capable to maintain the supply continuity and, whole plant not shut down. Hence, additional peak load diesel plant obviously enhance the safety of electrical auxiliary power supply system and at any nuclear power plant, it’s safety is the highest priority.
Title: Analysis of Neutronics and Kinetics Safety Parameters of 3 MW TRIGA Mark-II Research Reactor using Deterministic Code System SRAC2006
Biography:
Abstract:
