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Physics-Informed Neural Network Solution of Point Kinetics Equations for a Nuclear Reactor Digital Twin
A digital twin (DT) for nuclear reactor monitoring can be implemented using either a differential equations-based physics model or a data-driven machine learning model. The challenge of a physics-model-based DT consists of achieving sufficient model fidelity to represent a complex experimental system, whereas the challenge of a data-driven DT consists of extensive training requirements and a potential lack of predictive ability. We investigate the performance of a hybrid approach, which is based on physics-informed neural networks (PINNs) that encode fundamental physical laws into the loss function of the neural network. We develop a PINN model to solve the point kinetic equations (PKEs), which are time-dependent, stiff, nonlinear, ordinary differential equations that constitute a nuclear reactor reduced-order model under the approximation of ignoring spatial dependence of the neutron flux. The PINN model solution of PKEs is developed to monitor the start-up transient of Purdue University Reactor Number One (PUR-1) using experimental parameters for the reactivity feedback schedule and the neutron source. The results demonstrate strong agreement between the PINN solution and finite difference numerical solution of PKEs. We investigate PINNs performance in both data interpolation and extrapolation. For the test cases considered, the extrapolation errors are comparable to those of interpolation predictions. Extrapolation accuracy decreases with increasing time interval.
Journal Article
Safety in design
Sales Handles: Describes and makes a case for the use of High Temperature Gas-cooled Reactors as better and safer reactors over the currently used Light Water Reactors - Describes the application of the concept of intrinsic continuous process safeguarding in the chemical industry to other fields of society as well, including transportation, farming, the building trade, and leisure - The concept of intrinsic process safeguarding in the chemical industry comprises that the protection of reaction systems is based on their chemical and physical properties and is therefore not endangered by human errors or failures of instrumentation - Includes the description of approximately 70 accidents/incidents - Teaches the reader where applicable to integrate the safety of a design into the design itself - Recommends safe nuclear reactors Market description: Chemical, Civil, Mechanical, Risk, Safety Engineers, Chemists, Physicists, Managers (technical, production, business), Process Safety professionals, HSE professionals Government personnel involved in regulating and overseeing chemical plants and procedures as well as in traffic, storage, production etc Insurers, especially those dealing with catastrophic loss potentials-- Provided by publisher.
Book
Neutronics design of shutdown and control systems for a Zero Power Experiments of chloride-based molten salt fast reactor
Nuclear power’s role as a reliable, baseload, low-carbon source and its importance in achieving clean energy goals are being increasingly recognized with growing urgency around decarbonization of the global energy systems. However, to deliver a long-term sustainable solution, it is essential to develop innovative nuclear technologies for improving the fuel utilization and reducing the nuclear waste disposal challenge. Zero Power Reactors (ZPR) are an essential initial step for developing new nuclear technologies because they allow for testing and refinement in a safe environment before large-scale deployment. This paper discusses the design of a ZPR experiments for the development of iMAGINE, a novel chloride-based molten salt reactor technology. The paper presents a detailed analysis of the neutronic design for the shutdown and control systems of an experimental ZPR based on the iMAGINE molten salt reactor technology. The study concludes that a split-core design with a lower corner reflector as an extension of the lower annular reflector offers the most robust ZPR configuration, offering optimum operational margins and maneuverability. This design ensures safety, regulatory compliance, and sufficient control and shutdown performance for the successful development of the iMAGINE technology.
Journal Article
Exploring medical and public health preparedness for a nuclear incident : proceedings of a workshop
\"The National Academies of Sciences, Engineering, and Medicine held a workshop on August 22-23, 2018, in Washington, DC, to explore medical and public health preparedness for a nuclear incident. The event brought together experts from government, nongovernmental organizations, academia, and the private sector to explore current assumptions behind the status of medical and public health preparedness for a nuclear incident, examine potential changes in these assumptions in light of increasing concerns about the use of nuclear warfare, and discuss challenges and opportunities for capacity building in the current threat environment. This publication summarizes the presentations and discussions from the workshop.\"--Publisher's description.
Book
China prepares to test thorium-fuelled nuclear reactor
If China’s experimental reactor is a success it could lead to commercialization and help the nation meet its climate goals.
If China’s experimental reactor is a success it could lead to commercialization and help the nation meet its climate goals.
Journal Article
Ageing Management for Research Reactors
This Safety Guide provides practical guidance and recommendations on ageing management for research reactors, to meet the relevant requirements of IAEA Safety Standards Series No. SSR-3, Safety of Research Reactors. It is intended for use by operating organizations in establishing, implementing and improving ageing management programmes for research reactors, and by regulatory bodies in verifying that ageing of research reactors is being effectively managed. The Safety Guide focuses on managing the physical ageing of systems, structures and components important to safety, and also provides guidance on safety aspects of managing obsolescence. This Safety Guide is a revision of IAEA Safety Standards Series No. SSG-10, which it supersedes.
eBook
Guidelines for Ageing Management, Modernization and Refurbishment Programmes for Research Reactors
This publication provides detailed information for operating organizations of research reactors on methodologies to manage existing and potential ageing effects and the degradation of structures, systems and components.
eBook
The joint evaluated fission and fusion nuclear data library, JEFF-3.3
The joint evaluated fission and fusion nuclear data library 3.3 is described. New evaluations for neutron-induced interactions with the major actinides
235
U
,
238
U
and
239
Pu
, on
241
Am
and
23
Na
,
59
Ni
, Cr, Cu, Zr, Cd, Hf, W, Au, Pb and Bi are presented. It includes new fission yields, prompt fission neutron spectra and average number of neutrons per fission. In addition, new data for radioactive decay, thermal neutron scattering, gamma-ray emission, neutron activation, delayed neutrons and displacement damage are presented. JEFF-3.3 was complemented by files from the TENDL project. The libraries for photon, proton, deuteron, triton, helion and alpha-particle induced reactions are from TENDL-2017. The demands for uncertainty quantification in modeling led to many new covariance data for the evaluations. A comparison between results from model calculations using the JEFF-3.3 library and those from benchmark experiments for criticality, delayed neutron yields, shielding and decay heat, reveals that JEFF-3.3 performes very well for a wide range of nuclear technology applications, in particular nuclear energy.
Journal Article