Risk perception and public involvement have become more and more important in post-Fukushima accident era. A survey had been carried out about public acceptance of constructing coastal/inland Nuclear ...Power Plants (NPPs) in China. We examined impact factors of public acceptance of nuclear energy and also carried out a comparison between China and OECD. The study revealed that the public still took relatively optimistic attitude although there was a slight decrease just after Fukushima and the public's confidence recovered four years later. The ratio of inland NPPs opponents reached to quite a high level and “not-in-my-back-yard” still reflected an obvious syndrome. We also found public acceptance is mainly affected by benefit and, to a lesser extent, by knowledge, education and age. Moreover, the study suggested government is still a creditable information resource due to its authority but most of respondents felt little or no well-informed about nuclear safety, which means a significant communication gap exists between government and the public. As China is the most ambitious country to develop nuclear energy, it is proposed to introduce a transparent and open system of third-party evaluation, which mainly consists of scientists and non-profit research institutions, to ensure the healthy and sustainable development of nuclear energy.
•The public are more optimistic about nuclear energy in China than in OECD.•The ratio of inland nuclear power plants opponents reaches to quite a high level.•Government is still a creditable information resource due to its authority.•Third-party evaluation is proposed to intervene in nuclear safety supervision.
Advanced nuclear systems, such as fusion systems, generally have features of large size, complex structures, spatially heterogeneous distribution of components and materials, and high energy and high ...flux, as well as a wide and complex energy spectrum of neutrons. Compared with traditional nuclear systems, these features have brought unprecedented challenges to neutronics design and analysis. To confront these challenges, the FDS Team has made significant progress in the development of neutronics methods and the comprehensive simulation code Super Multi-functional Calculation Program for Nuclear Design and Safety Evaluation (SuperMC). Furthermore, the FDS Team has been developing the High Intensity D-T Fusion Neutron Generator (HINEG) and has performed a series of neutronics experiments. Based on the developed methods, codes, and facility, a series of fusion designs and analyses has been carried out, including the design of FDS series reactors as well as the ITER neutronics analysis.
In 2011, the Chinese Academy of Sciences launched an engineering project to develop an accelerator-driven subcritical system (ADS) for nuclear waste transmutation. The China Lead-based Reactor ...(CLEAR), proposed by the Institute of Nuclear Energy Safety Technology, was selected as the reference reactor for ADS development, as well as for the technology development of the Generation IV lead-cooled fast reactor. The conceptual design of CLEAR-I with 10 MW thermal power has been completed. KYLIN series lead-bismuth eutectic experimental loops have been constructed to investigate the technologies of the coolant, key components, structural materials, fuel assembly, operation, and control. In order to validate and test the key components and integrated operating technology of the lead-based reactor, the lead alloy-cooled non-nuclear reactor CLEAR-S, the lead-based zero-power nuclear reactor CLEAR-0, and the lead-based virtual reactor CLEAR-V are under realization.
•The new developed CAD-based Monte Carlo program named SuperMC for integrated simulation of nuclear system makes use of hybrid MC-deterministic method and advanced computer technologies. SuperMC is ...designed to perform transport calculation of various types of particles, depletion and activation calculation including isotope burn-up, material activation and shutdown dose, and multi-physics coupling calculation including thermo-hydraulics, fuel performance and structural mechanics. The bi-directional automatic conversion between general CAD models and physical settings and calculation models can be well performed. Results and process of simulation can be visualized with dynamical 3D dataset and geometry model. Continuous-energy cross section, burnup, activation, irradiation damage and material data etc. are used to support the multi-process simulation. Advanced cloud computing framework makes the computation and storage extremely intensive simulation more attractive just as a network service to support design optimization and assessment. The modular design and generic interface promotes its flexible manipulation and coupling of external solvers.•The new developed and incorporated advanced methods in SuperMC was introduced including hybrid MC-deterministic transport method, particle physical interaction treatment method, multi-physics coupling calculation method, geometry automatic modeling and processing method, intelligent data analysis and visualization method, elastic cloud computing technology and parallel calculation method.•The functions of SuperMC2.1 integrating automatic modeling, neutron and photon transport calculation, results and process visualization was introduced. It has been validated by using a series of benchmarking cases such as the fusion reactor ITER model and the fast reactor BN-600 model.
Monte Carlo (MC) method has distinct advantages to simulate complicated nuclear systems and is envisioned as a routine method for nuclear design and analysis in the future. High-fidelity simulation with MC method coupled with multi-physics phenomena simulation has significant impact on safety, economy and sustainability of nuclear systems. However, great challenges to current MC methods and codes prevent its application in real engineering projects. SuperMC, developed by the FDS Team in China, is a CAD-based Monte Carlo program for integrated simulation of nuclear systems by making use of hybrid MC and deterministic methods and advanced computer technologies. The design objective, architecture and main methodology of SuperMC are presented in this paper. SuperMC2.1, the latest version, can perform neutron, photon and coupled neutron and photon transport calculation, geometry and physics modeling, results and process visualization. It has been developed and verified by using a series of benchmarking cases such as the fusion reactor ITER model and the fast reactor BN-600 model. SuperMC is still in its evolution process toward a general and routine tool for the simulation of nuclear systems.
Summary
Research and development of safe and efficient nuclear energy systems is imperative, since nuclear safety is the key issue in the development of nuclear energy, and it is also the premise of ...nuclear energy development learned from the painful lessons in history. Advanced numerical simulation can restore the complex physical processes as much as possible and predict system behavior and safety performance, and it facilitates accurate design and assessment. International research in nuclear safety simulation has developed from single physical phenomena simulation to coupling simulation with digital reactor and to comprehensive simulation with virtual nuclear power plant by integrating environmental and social information. Compared with digital reactor, virtual nuclear power plant pays more attention to the evolution of reactor accidents, such as large‐scale physical and social behavior simulation, which concerned the relationship between nuclear safety and environment, as well as the relationship between the nuclear safety and the public. FDS Team proposed “nuclear informatics” firstly by combining nuclear science and informatics and has developed the virtual nuclear power plant in digital society environment Virtual4DS, where many key technologies are developed under the guidance of nuclear informatics, such as integration cloud architecture, automatic accurate modeling, multiphysics coupling simulation, multidimensional information visualization and virtual simulation, and nuclear big data. Virtual4DS has been widely used in the nuclear power plant, nuclear weapons, well logging, etc.
In this study, the structural integrity of liquid metal fast reactor fuel
assembly has been established for different parameters considering the
optimum fuel design. Analytical calculation of added ...mass effect due to lead
bismuth eutectic and verification through previously presented theories, has
been established. The integrity of the hexagonal wrapper of fuel assembly
has been guaranteed over the entire operating temperature range. Effect of
temperature on the density of lead bismuth eutectic, the subsequent
change in added mass of lead bismuth eutectic, the effect on natural
frequencies and effect on stresses on wrapper, has been studied in detail. A
simple empirical relationship is presented for estimation of added mass
effect for lead bismuth eutectic type fast reactors for any desired
temperature. An approach for assessment of fast reactor fuel assembly
performance has been outlined and calculated results are presented. Nuclear
seismic rules require that systems and components which are important to
safety, shall be capable of bearing earthquake effects and their integrity
and functionality should be guaranteed. Mode shapes, natural frequencies,
stresses on wrapper and seismic aspect has also been considered using
ANSYS. Modal analysis has been compared in vacuum and lead bismuth eutectic
using the calculated added mass.
nema
•The idea of truncation plane is used to calculate the response matrix library.•The ANN is used to reconstruct the neutron field of the reactor.•We have verified this method in a homogenized ...assembly-level VENUS-3 reactor model.•The method was effective and available to reconstruct the in-core neutron spectrum.
Nowadays, there are many reconstruction methods base on the ex-core detectors to monitor the state of the core in real-time, but none of these methods can calculate the neutron spectrum which has always been an essential parameter in advanced reactors design, performance diagnoses and safe operation. Thus, by utilizing ex-core measurements, a reconstruction neutron field with energy distributions method based on artificial neural networks was proposed in this paper. Furthermore, in this study, in order to amplify the contribution of low-energy neutrons to the ex-core detectors, the idea of truncation plane is used to calculate the response matrix library. To validate the method, neutron field of pressure vessel regions and core regions in a homogenized assembly-level VENUS-3 reactor model were obtained through transport calculation and reconstruction calculation. The comparison of results demonstrated that the reconstruction method was effective and available to reconstruct the neutron spectrum in reactors.
China focuses on the development of the liquid LiPb blanket due to its attractive performances. A series of LiPb breeder blanket concepts were proposed for different applications of fusion in China. ...This paper gives an overview of the LiPb breeder blanket concepts and relevant R&D progress in China.
PDF
