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Michael Todosow

Bio: Michael Todosow is an academic researcher from Brookhaven National Laboratory. The author has contributed to research in topics: Nuclear fuel cycle & Light-water reactor. The author has an hindex of 15, co-authored 54 publications receiving 824 citations.


Papers
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Mohammad M. Alsharo'a1, C. Ankenbrandt2, M. Atac2, B. Autin3  +174 moreInstitutions (39)
TL;DR: In this paper, the status of the effort to realize a first neutrino factory and the progress made in understanding the problems associated with the collection and cooling of muons towards that end are described.
Abstract: We describe the status of our effort to realize a first neutrino factory and the progress made in understanding the problems associated with the collection and cooling of muons towards that end. We summarize the physics that can be done with neutrino factories as well as with intense cold beams of muons. The physics potential of muon colliders is reviewed, both as Higgs factories and compact high-energy lepton colliders. The status and time scale of our research and development effort is reviewed as well as the latest designs in cooling channels including the promise of ring coolers in achieving longitudinal and transverse cooling simultaneously. We detail the efforts being made to mount an international cooling experiment to demonstrate the ionization cooling of muons.

186 citations

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TL;DR: In this article, the performance of thorium-based fuels has been investigated in the light water reactor (LWR) nuclear fuel cycle. But, the main sources of proliferation potential and radiotoxicity are the plutonium and higher actinides generated during the burnup of standard LWR fuel, and a significant reduction in the quantity and quality of generated Pu can be achieved by replacing the 238 U fertile component of conventional low-enriched uranium fuel by 232 Th Thorium.
Abstract: Thorium-based fuels can be used to reduce concerns related to the proliferation potential and waste disposal of the conventional light water reactor (LWR) uranium fuel cycle The main sources of proliferation potential and radiotoxicity are the plutonium and higher actinides generated during the burnup of standard LWR fuel A significant reduction in the quantity and quality of the generated Pu can be achieved by replacing the 238 U fertile component of conventional low-enriched uranium fuel by 232 Th Thorium can also be used as a way to manage the growth of plutonium stockpiles by burning plutonium, or achieving a net-zero transuranic production, sustainable recycle scenario This paper summarizes some of the results of recent studies of the performance of thorium-based fuels It is concluded that the use of heterogeneous U-Th fuel provides higher neutronic potential than a homogeneous fuel However, in the former case, the uranium portion of the fuel operates at a higher power density, and care is needed to meet the thermal margins and address the higher-burnup implications In macroheterogeneous designs, the U-Th fuel can yield reduced spent-fuel volume, toxicity, and decay heat The main advantage of Pu-Th oxide over mixed oxide is better void reactivity behavior even for undermoderated designs, and increased burnup of Pu

73 citations

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TL;DR: In this article, an operational assessment of four different candidate composite materials was performed for nominal conditions in a reference PWR with Zr-based cladding, and the impact of UN porosity on the operational performance was assessed.

65 citations

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TL;DR: In this article, the authors evaluated UN-U3Si5 fuel with Kanthal AF or APMT cladding and showed that the UO2-Zr fuel claddings performed similar to the zirconium alloy cladding in terms of safety coefficients.

60 citations

Journal ArticleDOI
TL;DR: In this paper, the results of the lattice-level neutronic study of doubly heterogeneous FCM fuel were presented, and the results showed that the linear reactivity model does not provide a good estimate of the fuel cycle length, due primarily to nonlinear reactivity behavior at high burn-up (>800 effective full power days).

58 citations


Cited by
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TL;DR: In this paper, the subject of quantum electrodynamics is presented in a new form, which may be dealt with in two ways: using redundant variables and using a direct physical interpretation.
Abstract: THE subject of quantum electrodynamics is extremely difficult, even for the case of a single electron. The usual method of solving the corresponding wave equation leads to divergent integrals. To avoid these, Prof. P. A. M. Dirac* uses the method of redundant variables. This does not abolish the difficulty, but presents it in a new form, which may be dealt with in two ways. The first of these needs only comparatively simple mathematics and is directly connected with an elegant general scheme, but unfortunately its wave functions apply only to a hypothetical world and so its physical interpretation is indirect. The second way has the advantage of a direct physical interpretation, but the mathematics is so complicated that it has not yet been solved even for what appears to be the simplest possible case. Both methods seem worth further study, failing the discovery of a third which would combine the advantages of both.

1,398 citations

Journal ArticleDOI
01 Jun 2014
TL;DR: The Serpent Monte Carlo reactor physics burnup calculation code has been developed at VTT Technical Research Centre of Finland since 2004, and is currently used in over 100 universities and research organizations around the world.
Abstract: The Serpent Monte Carlo reactor physics burnup calculation code has been developed at VTT Technical Research Centre of Finland since 2004, and is currently used in over 100 universities and research organizations around the world. This paper presents the brief history of the project, together with the currently available methods and capabilities and plans for future work. Typical user applications are introduced in the form of a summary review on Serpent-related publications over the past few years.

864 citations

Journal ArticleDOI
01 May 1978
TL;DR: In this article, the authors have considered the interests of both scientists and practising engineers, in addition to serving the needs of the academia, in order to avoid lengthy and repetitive discussions, that are available in many standard text books on reactor physics.
Abstract: This is cne of the r-are text books written in the discipline of Nuclear Reactor Analysis, where the author has considered the interests of both scientists and practising engineers, in addition to serving the needs of the academia. The most attractive feature of this book is a balanced treatment of theory and practice of the subject matter. The theoretical foundations of the reactor design methods are explained with simplified definitions and relevant practical illustrations. The author scans through quickly the traditional aspects of the so-called reactor physics and takes the reader through the details of the analytical aspects in a conventional manner. Hcwever, there is a definite departure from the classical method of approach in order to avoid lengthy and repetitive discussions, that are available in many standard text books on reactor physics. The chief departure fran tradition is the priority accorded to the treatment of the energy part of the problems as opposed to the spatial Dart normally devoted to by other authors . A similar unorthodox approach has been applied while dealing with the solution of the various equations by giving priority to computer oriented mrethods as opposed to the classical solutions.

507 citations

Journal ArticleDOI
TL;DR: A review of the development status for three accident tolerant fuel cladding technologies, namely coated zirconium-based cladding, ferritic alumina-forming alloy cladding and silicon carbide fiber-reinforced SCCM composite, is offered in this paper.

494 citations