Catalogue Search | MBRL
Search Results Heading
Explore the vast range of titles available.
MBRLSearchResults
-
DisciplineDiscipline
-
Is Peer ReviewedIs Peer Reviewed
-
Series TitleSeries Title
-
Reading LevelReading Level
-
YearFrom:-To:
-
More FiltersMore FiltersContent TypeItem TypeIs Full-Text AvailableSubjectCountry Of PublicationPublisherSourceTarget AudienceDonorLanguagePlace of PublicationContributorsLocation
Done
Filters
Reset
191,766
result(s) for
"Nuclear reactors"
Sort by:
Physics-Informed Neural Network Solution of Point Kinetics Equations for a Nuclear Reactor Digital Twin
by
Prantikos, Konstantinos
,
Tsoukalas, Lefteri H.
,
Heifetz, Alexander
in
Big Data
,
Differential equations
,
digital twin
2022
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.
Ageing Management for Research Reactors
by
IAEA
in
Nuclear reactors-Decommissioning
,
Nuclear reactors-Research
,
Nuclear reactors-Safety measures
2023
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.
Exploring medical and public health preparedness for a nuclear incident : proceedings of a workshop
by
Exploring Medical and Public Health Preparedness for a Nuclear Incident (Workshop) (2018 : Washington, DC)
,
Pray, Leslie A., rapporteur
,
Kahn, Benjamin, rapporteur
in
Nuclear accidents United States Management Planning Congresses.
,
Emergency management United States Congresses.
,
Nuclear reactors United States Safety measures Congresses.
\"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.
Neutronics design of shutdown and control systems for a Zero Power Experiments of chloride-based molten salt fast reactor
by
Noori-kalkhoran, Omid
,
Aflyatunova, Daliya
,
Powell, Lewis
in
Carbon sources
,
Chloride
,
Chlorides
2024
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
China prepares to test thorium-fuelled nuclear reactor
2021
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
Life Exposed
2013
On April 26, 1986, Unit Four of the Chernobyl nuclear reactor exploded in then Soviet Ukraine. More than 3.5 million people in Ukraine alone, not to mention many citizens of surrounding countries, are still suffering the effects.Life Exposedis the first book to comprehensively examine the vexed political, scientific, and social circumstances that followed the disaster. Tracing the story from an initial lack of disclosure to post-Soviet democratizing attempts to compensate sufferers, Adriana Petryna uses anthropological tools to take us into a world whose social realities are far more immediate and stark than those described by policymakers and scientists. She asks: What happens to politics when state officials fail to inform their fellow citizens of real threats to life? What are the moral and political consequences of remedies available in the wake of technological disasters?
Through extensive research in state institutions, clinics, laboratories, and with affected families and workers of the so-called Zone, Petryna illustrates how the event and its aftermath have not only shaped the course of an independent nation but have made health a negotiated realm of entitlement. She tracks the emergence of a \"biological citizenship\" in which assaults on health become the coinage through which sufferers stake claims for biomedical resources, social equity, and human rights.Life Exposedprovides an anthropological framework for understanding the politics of emergent democracies, the nature of citizenship claims, and everyday forms of survival as they are interwoven with the profound changes that accompanied the collapse of the Soviet Union.
Evaluating Nuclear Forensic Signatures for Advanced Reactor Deployment: A Research Priority Assessment
by
Peterson, Appie A.
,
Schiferl, Megan N.
,
Abergel, Rebecca J.
in
advanced reactors
,
Chemical composition
,
Detonation
2024
The development and deployment of a new generation of nuclear reactors necessitates a thorough evaluation of techniques used to characterize nuclear materials for nuclear forensic applications. Advanced fuels proposed for use in these reactors present both challenges and opportunities for the nuclear forensic field. Many efforts in pre-detonation nuclear forensics are currently focused on the analysis of uranium oxides, uranium ore concentrates, and fuel pellets since these materials have historically been found outside of regulatory control. The increasing use of TRISO particles, metal fuels, molten fuel salts, and novel ceramic fuels will require an expansion of the current nuclear forensic suite of signatures to accommodate the different physical dimensions, chemical compositions, and material properties of these advanced fuel forms. In this work, a semi-quantitative priority scoring system is introduced to identify the order in which the nuclear forensics community should pursue research and development on material signatures for advanced reactor designs. This scoring system was applied to propose the following priority ranking of six major advanced reactor categories: (1) molten salt reactor (MSR), (2) liquid metal-cooled reactor (LMR), (3) very-high-temperature reactor (VHTR), (4) fluoride-salt-cooled high-temperature reactor (FHR), (5) gas-cooled fast reactor (GFR), and (6) supercritical water-cooled reactor (SWCR).
Journal Article