Innovative Nuclear Energy Systems Research Articles

Solving the issue of reliability data for FOAK equipment in an innovative nuclear energy system

There is a demand for the improved safety and economics of advanced nuclear energy systems. The world's first high-temperature gas-cooled reactor pebble-bed module nuclear power plant (HTR-PM Demo Project) is about to be completed in China. This power plant achieved initial full power at the end of 2022. The success of the HTR-PM Demo Project shows the importance of risk-informed initiatives throughout the project with solid support from comprehensive risk assessment. This paper focuses on a technical issue that needs to be solved when conducting risk-informed initiatives for HTR-PM, namely the issue of reliability data for first-of-a-kind (FOAK) equipment. In short, no data for the FOAK equipment are available in existing reliability databases. On the basis of the HTR-PM pilot experience, this paper proposes a process of estimating the required data for the reliability parameters of FOAK equipment. The process has five steps: (1) identification of key parts and assemblies, (2) preliminary determination of the reliability parameters and the associated reference values for the key parts and assemblies, (3) analysis of maintenance management tactics, (4) estimation of reliability parameters for the FOAK equipment using a Bayesian network, and (5) Bayesian updating with operational data. The helium circulator of HTR-PM is taken as an example to demonstrate the feasibility of the proposed process. A lack of reliability data is a common issue for innovative nuclear energy systems. The proposed process is supposed to be universal to all types of innovative design.

Comparative evaluation of different options for energy system development in small countries

In this paper an approach, proposed in the frame of the IAEA International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) and its Collaborative Project “Key indicators for innovative nuclear energy systems” (KIND) for a multi-criteria comparative assessment of different energy options was studied and applied. Comparative evaluation of two hypothetical energy systems - nuclear and non-nuclear was performed in the context of co-operation between small countries in the Balkan region. The evaluation was based on various criteria grouped into selected areas to cover different dimensions in terms of sustainability - economic, environment, public, safety, infrastructure. The results show that nuclear option obtained higher total scores and is thus the preferred option. The nuclear option performs better in the areas of economics, environment and national security and non-nuclear option has the advantage in areas of waste management, safety, public acceptance and infrastructure. The sensitivity and uncertainty analysis performed in the study enable to consider the impact of the input uncertainties on the ranking results and their stability. The study could be used to support decision makers in energy policy at national level, demonstrating the application of methodology.

Preface: 19th International Conference on Emerging Nuclear Energy Systems (ICENES 2019)

This is an exclusively prepared special issue containing selected papers from well-established events, namely, International Conference on Emerging Nuclear Energy Systems (ICENES) and some invited papers to enrich and broaden the novelty of nuclear energy technologies and its applications. The 19th International Conference on Emerging Nuclear Energy Systems (ICENES 2019) is one of the international conference on scientific, engineering, education and other technical aspects of innovative nuclear reactor design, advanced nuclear technology, energy related technology and its applications.The conference was held in Holiday Inn, Bali, Indonesia (6-9 October 2019), organized by the Bandung Institute of Technology (ITB) and in cooperation with the International Atomic Energy Agency (IAEA). The participants come from several 14 countries and from many institutions from universities, governments, companies, society and some other organizations that shared their ideas and research results on emerging nuclear energy technologies and applications, which covered by keynote speakers, invited and contributed oral talks and poster presentations. Some selected presented paper in the conference have been elected as selected papers after reviewing process to be submitted to the Institute of Physics (IoP), Journal of Physics: Conference Series.Nuclear energy recently is recognized as secure, sustain and green energy source as an ultimate energy resource to secure the future of the mankind and its civilization. Hence, considerable research activities and international collaboration are continuing on innovative nuclear energy systems, reactor physics, radiations and its application, nuclear computational system, including fusion energy technology, fusion-fission hybrids systems, GEN-IV reactors technology, small and modular reactor (MSR) technology, space nuclear reactors, and power systems and accelerator-driven systems technologies. Some related topics are also covered related to nuclear power production; nuclear hydrogen production; hydrogen energy, energy efficiency, and management; solar energy; wind energy; hydrogen production and storage; renewable energy; fuel cells; bio-energy, etc.Finally, on behalf of the organizer and advisory board, we would like to express my sincere appreciation and gratitude to all of authors during the conference and publication processes for their valuable contributions and to the members of the committee, reviewers, and advisors for their excellent works in preparing and finalizing this document. We apologize for any inconveniences for this long process of publication due to our conditions and some restrictions as well as some difficulties during COVID19 pandemicList of Organizer, Editorial Board are available in this Pdf.

Full Core Criticality Modeling of Gas-Cooled Fast Reactor using the SCALE6.0 and MCNP5 Code Packages

The Gas-Cooled Fast Reactor (GFR) is one of the reactor concepts selected by the Generation IV International Forum (GIF) for the next generation of innovative nuclear energy systems. It was selected among a group of more than 100 prototypes and his commercial availability is expected by 2030. GFR has common goals as the rest GIF advanced reactor types: economy, safety, proliferation resistance, availability and sustainability. Several GFR fuel design concepts such as plates, rod pins and pebbles are currently being investigated in order to meet the high temperature constraints characteristic for a GFR working environment. In the previous study we have compared the fuel depletion results for heterogeneous GFR fuel assembly (FA), obtained with TRITON6 sequence of SCALE6.0 with the results of the MCNPX-CINDER90 and TRIPOLI-4-D codes. Present work is a continuation of neutronic criticality analysis of heterogeneous FA and full core configurations of a GFR concept using 3-D Monte Carlo codes KENO-VI/SCALE6.0 and MCNP5. The FA is based on a hexagonal mesh of fuel rods (uranium and plutonium carbide fuel, silicon carbide clad, helium gas coolant) with axial reflector thickness being varied for the purpose of optimization. Three reflector materials were analyzed: zirconium carbide (ZrC), silicon carbide (SiC) and natural uranium. ZrC has been selected as a reflector material, having the best contribution to the neutron economy and to the reactivity of the core. The core safety parameters were also analysed: a negative temperature coefficient of reactivity was verified for the heavy metal fuel and coolant density loss. Criticality calculations of different FA active heights were performed and the reflector thickness was also adjusted. Finally, GFR full core criticality calculations using different active fuel rod heights and fixed ZrC reflector height were done to find the optimal height of the core. The Shannon entropy of the GFR core fission distribution was proved to be useful technique to monitor both fission source convergence (stationarity) and core eigenvalue convergence (keff) to fundamental eigenmode with MCNP5. All calculations were done with ENDF/B-VII.0 library. The obtained results showed high similarity with reference results.

Ti3AlC2, a candidate structural material for innovative nuclear energy system: The microstructure phase transformation and defect evolution induced by energetic heavy-ion irradiation

For the structure materials applied in the innovative nuclear energy system, the strongly environment radiation source is always a big concern which will severely degrade the materials performance especially at high temperature. To explore the mechanisms of the anti-irradiation properties in Ti3AlC2, a typical MAX phase material showing excellent irradiation damage tolerance and resistance to amorphization, we conducted a series of 1 MeV C4+ ions irradiation experiments on them at different temperatures (RT, 300°C, 500°C and 800°C). Through Grazing Incidence X-ray Diffraction (GIXRD), Raman spectra (Raman), slow positron annihilation Doppler Broadening Spectroscopy (DBS) and high resolution Transmission Electron Microscopy (HRTEM), the anti-irradiation properties were systematically investigated. For the first time, an entire microstructure phase transformation process of Ti3AlC2 from α to β to γ and to perfect fcc structure phase induced by irradiation at RT and it is inverse (recovery) process of phase transformation under high temperature (≥300 °C) irradiation conditions are found and confirmed. And lots of simple vacancies are induced by irradiation and the density of them gets saturated above 5 × 1015 ions/cm2 fluences. These processes of phase transformation and recovery and vacancy saturation phenomenon are the primary reasons for why Ti3AlC2 has excellent irradiation damage tolerance and resistance to amorphization. In addition, the micro strain and lattice parameters are also affected by microstructure transformation and have been discussed. In a word, Ti3AlC2 materials show good anti-irradiation properties especially at high temperature, and now it is a primary candidate as the coating of the cladding material and the spallation target beam windows material in Chinese ADS project. And studies on this kind of materials provide a promising new concept and way for designing the structural materials for innovative nuclear energy system.

Generation-IV nuclear reactor systems

In this paper, we provide a concise description of the six nuclear reactor concepts that are under development in the framework of the Generation-IV International Forum. After a brief introduction on the world energy needs, its plausible evolution during the next fifty years, and the constraints imposed by the necessity to address the climate challenges we are facing today, we will present the main features of the innovative nuclear energy systems that hold the promise to produce almost-zero-carbon-emission electricity, heat for chemistry and industrial manufacturing, hydrogen to be used as energy vector, and affordable freshwater. Potential advantages over currently available nuclear systems in terms of increased safety, reduced proliferation risks, economical affordability, sustainability of the fuel cycle, and management of the waste inventory will be critically discussed against the technical challenges that remain to be overcome.

Forecasting System Requirements to the Materials of the Shell of Fuel Elements of Innovative Fast Reactors

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PREFACE for the special issue on “progress in novel nuclear energy technologies”

This is an exclusively prepared special issue containing papers selected from two well-established events, namely, International Conference on Emerging Nuclear Energy Systems (ICENES) and International Conference on Nuclear and Renewable Energy Resources (NURER) and some invited papers in order to make a unique source to reflect the progress in the area of novel nuclear energy technologies. ICENES, with a long scientific tradition, started in 1978 as an autonomous, self-organized event by a group of independent nuclear scientists. The goal was to find unconventional new routes for improving the use of the atomic energy beyond the commercial grounds. It was evident that the field of “strong interactions” still has a broad way for further developments to harness the most powerful source of energy of our universe, in a safe way and with better use of natural resources. The Nuclear Field is plenty of opportunities, and no free from risks, and it is the spirit of human vocation to explore those domains where new findings can change some essential aspects of our world, as is the case of Energy. Nuclear energy is considered the ultimate energy to secure the future of the mankind. Hence, considerable research activities and international collaboration are continuing on innovative nuclear energy systems, such as fusion energy, fusion-fission hybrids, GEN-IV reactors, space nuclear reactors, and power systems and accelerator-driven systems. Asian countries are considerably progressing in the construction of new nuclear reactor as well as in the research and the development of innovative nuclear energy technologies. A sort of new international merging is needed to recover capability and potential in this field of Physics and Technology, which should play an important role in coping with the energy problem and its environmental effects. NURER is a relatively younger one, which was initiated in 2010 as an independent event to look inside the long-term future of energy problems, without forgetting to bridge the gap between the present time and the future, parallel to the ICENES series in alternating years. Both are unique conferences in their nature, considering that nuclear energy, and other newly emerging alternative and renewable energy technologies as complementing and not competing directions with each other. On that way, ICENES and NURER conferences represent two alternating fora, where present and future technologies and systems are discussed under the same umbrella and establish a bridge with closer communication and mutual understanding between nuclear and renewable energy communities. The mankind needs both of them. In that sense, both conferences cover a wide range of topics related to nuclear power production; nuclear hydrogen production; hydrogen energy, energy efficiency, and management; solar energy; wind energy; hydrogen production and storage; renewable energy; fuel cells; bio-energy, etc. In closing, this particular special issue aims to make a unique collection on “progress in novel nuclear energy technologies” from the papers selected from the above listed conferences along with some invited papers which have peer-reviewed, improved, enhanced, and accepted for publication in IJER. The guest editor would like to take this opportunity to warmly thank the editor-in-chief, Prof Dr Ibrahim Dincer; Journal Manager, Peter Creaton; and the authors of the special issue papers to make this special issue a fruitful outcome.

A Roadmap of Innovative Nuclear Energy System

Nuclear is a dense energy without CO2 emission. It can be used for more than 100,000 years using fast breeder reactors with uranium from the sea. However, it raises difficult problems associated with severe accidents, spent fuel waste and nuclear threats, which should be solved with acceptable costs. Some innovative reactors have attracted interest, and many designs have been proposed for small reactors. These reactors are considered much safer than conventional large reactors and have fewer technical obstructions. Breed-and-burn reactors have high potential to solve all inherent problems for peaceful use of nuclear energy. However, they have some technical problems with materials. A roadmap for innovative reactors is presented herein.

Probabilistic risk assessment from potential exposures to the public applied for innovative nuclear installations

Potential exposures are those that may occur as a result of unanticipated operational performance or accidents. Potential exposure situations are probabilistic in nature because they depend on uncertain events such as equipment failure, operator errors or external initiators beyond the control of the operator. Consequently, there may exist a range of possible radiological impacts that need to be considered. In this paper a Level 3 Probabilistic Safety Assessment (PSA) for a hypothetical scenario relevant to Innovative Nuclear Energy Systems (INS) was conducted using computer code MACCS (MELCOR Accident Consequence Code Systems). The acceptability of an INS was analyzed taking into account the general requirement that relocation or evacuation measures must not be necessary beyond the site boundary. In addition, deterministic modeling of the accident consequences for the critical meteorological conditions was carried out using the JRODOS decision support system (Real-time On-line Decision Support system for off-site emergency management in Europe). The approach used for dose and risk assessment from potential exposure of accidental releases and their comparison with acceptance criteria are presented. The methodology described can be used as input to the licensing procedure and engineering design considerations to help satisfy relevant health and environmental impact criteria for fission or fusion nuclear installations.

Innovative Nuclear Energy Systems: State-of-the Art Survey on Evaluation and Aggregation Judgment Measures Applied to Performance Comparison

This paper summarizes the experience gained in the application of multi-criteria decision making and uncertainty treatment methods to a comparative assessment of nuclear energy systems and related nuclear fuel cycles. These judgment measures provide a means for comprehensive evaluation according to different conflicting criteria, such as costs, benefits and risks, which are inevitably associated with the deployment of advanced technologies. Major findings and recommendations elaborated in international and national projects and studies are reviewed and discussed. A careful analysis is performed for multi-criteria comparative assessment of nuclear energy systems and nuclear fuel cycles on the basis of various evaluation and screening results. The purpose of this paper is to discuss the lessons learned, to share the identified solutions, and indicate promising future directions.

INPRO Activities on Development of Advanced Tools to Support Judgment Aggregation for Comparative Evaluation of Nuclear Energy Systems

This paper presents first results of the INPRO Collaborative Project on Key Indicators for Innovative Nuclear Energy Systems, which has the objective to develop guidance and tools for comparative evaluation of the status, prospects, benefits, and risks associated with development of innovative nuclear technologies for a more distant future. Presented results illustrate expedience of application of the multicriteria decision analysis methods, which are able to provide the added value to comparative assessment of nuclear energy systems. First, the paper presents a short review of the multicriteria decision analysis methods appropriate to support judgment aggregation within comparative evaluations of nuclear energy systems based on key indicators and highlights the methodology to perform such assessments. Second, a set of key indicators elaborated in the INPRO Collaborative Project on Global Architecture of Innovative Nuclear Energy Systems Based on Thermal and Fast Reactors Including a Closed Fuel Cycle (GAINS) were evaluated for comparative evaluation of nuclear energy system evolution scenarios. Third, a numerical example is presented of application of the selected key indicators, methods, and tools for judgment aggregation in comparative assessment of the GAINS nuclear energy systems.

An approach for evaluating the integrity of fuel applied in Innovative Nuclear Energy Systems

One of the important issues in the study of Innovative Nuclear Energy Systems is evaluating the integrity of fuel applied in Innovative Nuclear Energy Systems. An approach for evaluating the integrity of the fuel is discussed here based on the procedure currently used in the integrity evaluation of fast reactor fuel. The fuel failure modes determining fuel life time were reviewed and fuel integrity was analyzed and compared with the failure criteria.Metal and nitride fuels with austenitic and ferritic stainless steel (SS) cladding tubes were examined in this study. For the purpose of representative irradiation behavior analyses of the fuel for Innovative Nuclear Energy Systems, the correlations of the cladding characteristics were modeled based on well-known characteristics of austenitic modified 316 SS (PNC316), ferritic–martensitic steel (PNC–FMS) and oxide dispersion strengthened steel (PNC–ODS).The analysis showed that the fuel lifetime is limited by channel fracture which is a nonductile type (brittle) failure associated with a high level of irradiation-induced swelling in the case of austenitic steel cladding. In case of ferritic steel, on the other hand, the fuel lifetime is controlled by cladding creep rupture. The lifetime evaluated here is limited to 200GWd/t, which is lower than the target burnup value of 500GWd/t. One of the possible measures to extend the lifetime may be reducing the fuel smeared density and ventilating fission gas in the plenum for metal fuel and by reducing the maximum cladding temperature from 650 to 600°C for both metal and nitride fuel.

INPRO Studies of Proliferation Resistance for DUPIC Fuel Cycle

The evaluation of proliferation resistance on the DUPIC fuel cycle was performed using the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) user manual. The user manual was finally published from INPRO as a tool for proliferation resistance evaluation. Five user requirements were well organized under one basic principle, and each evaluation parameter for each user requirement has criteria for qualitative and quantitative evaluation for an innovative nuclear system. The DUPIC fuel cycle is to fabricate CANDU fuel from spent pressurized water reactor fuel by use of a dry thermal process without separating the stable fission products. The DUPIC process and fabricated fuel have very intense radiation background and a low amount of fissile plutonium and uranium. The DUPIC fuel cycle has a number of intrinsic features that enhance proliferation resistance. The number of assemblies in the DUPIC process to get 1 significant quantity is very large ([approximately]48 assemblies). The assessment results using the user manual show that the DUPIC fuel cycle is very strong against nuclear proliferation by the material property itself and the facility condition. Additionally, several suggestions and conditions were made to increase the proliferation resistance for innovative future nuclear energy system.

An approach for evaluating fuel system applied in innovative nuclear energy system

One of the important issues in the study of Innovative Nuclear Energy Systems (INES) is the integrity of the fuel system applied. An approach of evaluating fuel system integrity is discussed here based on the procedure currently used in the integrity evaluation of fast reactor fuel. The fuel failure modes controlling fuel life were reviewed and fuel integrity was analyzed and compared with the failure criteria. Metal and nitride fuels with austenitic and ferritic cladding tubes were examined in this study. For the purpose of representative irradiation behavior analyses of the fuel for INES, the correlations of the cladding characteristics were modeled based on well-known characteristics of austenitic modified 316 SS (PNC316), ferritic-martensitic steel (PNC-FMS) and oxide dispersion strengthen steel (PNC-ODS). The analytical result showed that fuel lifetime is limited by channel fracture which is a nonductile type (brittle) failure associated with a high level of irradiation-induced swelling in the case of austenitic steel cladding. In the case of ferritic steel, on the other hand, the fuel life is controlled by cladding creep rupture. The lifetime evaluated here is no more than 200 GWd/t, which is still lower than the target value 400 GWd/t burnup. Possible measures to extend metal fuel lifetime may be reducing fuel smear density and ventilating fission gas in the plenum.

INPRO economic assessment of the IRIS nuclear reactor for deployment in Brazil

This paper presents the results of the economic assessment of the International Reactor Innovative and Secure (IRIS) for deployment in Brazil using the assessment methodology developed under the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO), co-ordinated by the International Atomic Energy Agency (IAEA). INPRO initiated in 2001 and has the main objective of helping to ensure that nuclear energy will be available to contribute in a sustainable manner to the energy needs of the 21st century. Among its missions is the development of a methodology to assess innovative nuclear energy systems (INSs) on a global, regional and national basis. In 2005, Brazil submitted a proposal for the assessment of two small-size reactors as components of an INS, completed with a conventional open nuclear fuel cycle based on enriched uranium. One of the reactors assessed was IRIS, a small-size, modular, integral-type PWR reactor. IRIS was evaluated with regard to the areas of reactor safety and economics only. This paper outlines the rationale for the study and summarizes the results of the economic assessment. The study concluded that the reference design of IRIS complies with most of INPRO economics criteria and has potential to comply with the remaining ones.

Comparison of MCNPX-C90 and TRIPOLI-4-D for fuel depletion calculations of a Gas-cooled Fast Reactor

The Gas-cooled Fast Reactor is one of the reactor concepts selected by the Generation IV International Forum for the next generation of innovative nuclear energy systems. Several fuel design concepts are being investigated. Burnup depletion of mixed fuel of uranium and plutonium, cooled with gas in a fast neutron energy spectrum must be simulated. Various codes are being developed and/or adapted to improve the quality of the results, and also to reduce the computing time required for the simulations. The main objective of this work is to compare the fuel depletion results obtained with MCNPX-CINDER90 code and the new TRIPOLI-4-Depletion 1 TRIPOLI® is a registered trademark of CEA. 1 code (developed by the Commissariat à l’Énergie Atomique) of a fuel design concept for the Gas-cooled Fast Reactor. Calculations were made for an equivalent homogeneous model of fuel rods in a hexagonal mesh assembly. Total reflection conditions were applied on the six lateral faces and the two axial faces of the assembly. The materials used in the fuel assembly are: carbide of uranium and plutonium as fuel, silicon carbide as cladding, and helium gas as coolant. JEFF libraries of effective cross sections were used in both codes. Two methods of burnup step calculations were performed with TRIPOLI-4-D, the Euler and the CSADA, and their results were compared with the MCNPX-CINDER90 CSADA method. A period of 300 days of irradiation time was considered, which was divided into 12 steps. Results of the infinite multiplication factor as function of the irradiation time, and the evolution of the isotope concentrations for a selected group of nuclides were compared. The main conclusion is that very similar results were obtained for the three types of depletion calculations which were compared: (1) MCNPX-C90 CSADA; (2) TRIPOLI-4-D CSADA, and (3) TRIPOLI-4-D EULER. The best calculation time was obtained with the TRIPOLI-4-D EULER method, which needed approximately half the time than the other two. In summary, it is sufficiently good to use the first order approximation (Euler method) for the time dependent fuel depletion simulation of the fast neutronic spectrum GFR fuel studied in this work.

Local Civic Forum: An experimental study promoting public acceptance on nuclear energy

In order to promote public acceptance on nuclear energy, an experimental study named “Local Civic Forum” has been performed as one of the research activities on relationship between nuclear energy and society promoted by the 21st Century Center of Excellence Program: “Innovative Nuclear Energy Systems for Sustainable Development of the World” conducted in Tokyo Institute of Technology (Tokyo Tech). The Local Civic Forum was designed to implement a dialogue among doctoral students of Tokyo Tech and multi-stakeholders of society. The framework of the forum looks like a stakeholder meeting or a consensus conference, however, it is different from these because no nuclear specialists directly join the dialogue. The specialists actively supported the doctoral students. The multi-stakeholders were selected from a viewpoint of social responsibility. Subjects in the Local Civic Forum were selected by the students from problems of nuclear energy. The participants of the forum discussed the selected subject based on the same eyes, and tried to get findings for hidden problems or issues on public acceptance of nuclear energy. We have made seven experiments of the forums between FY2005 and 2006. Some valuable comments were obtained from the participants to improve the scheme and management of the forum. It was found that the selection of multi-stakeholders and the facilitator of the Local Civic Forum played an important role. In this paper, the experimental results of the Local Civic Forum and the findings obtained by the participants will be presented.

Public Opinion Survey on the Relationship between Society and Nuclear Energy

The social research group of the 21st century COE program “Innovative Nuclear Energy Systems for Sustainable Development of the World” has studied under the theme coevolution of nuclear technology and society. As part of this study, this group conducted a questionnaire survey of 2,500 adults (collection rate of 22.0%; 551 replies) who live in the Tokyo metropolitan area. The purpose of this survey asking opinion about the relationship between attitude toward nuclear technology utilization and social awareness is to determine their request, exception and concern about nuclear technology utilization. The survey reveals that the differences of attitudes towards nuclear technology utilization can be explained in terms of differences of general views on the society, such as the directionality of social progress. Thus, it is necessary to argue with citizens about the strategy on nuclear technology utilization from the viewpoint of the directionality of the future society. The social decision-making process on nuclear technology utilization has to be renovated through dialogue among citizens as the partner taking on the achievement and contribution toward the directionality of the future society.

Innovative Nuclear Energy Systems and the Future of Nuclear Power

There is a renewed interest in nuclear power worldwide. The interest is sparked by concerns about global warming and security of energy supplies. In addition to the growing interest in building more reactors in countries that already have nuclear power, future demands for nuclear power are likely to include applications in countries that do not presently use nuclear power and applications beyond large-scale electricity generation. This paper will discuss some of the characteristics that future reactors will need to have to meet such demands, as well as other measures required to facilitate a nuclear renaissance. In addition, the emergence of new international nuclear initiatives and their potential roles will be described.