Last edited by Mazucage
Tuesday, May 19, 2020 | History

2 edition of Nuclear fuel cycle simulation system (VISTA). found in the catalog.

Nuclear fuel cycle simulation system (VISTA).

Nuclear fuel cycle simulation system (VISTA).

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  • 23 Currently reading

Published by International Atomic Energy Agency in Vienna .
Written in English

    Subjects:
  • Nuclear fuels.,
  • Reactor fuel reprocessing -- Simulation methods.

  • About the Edition

    The Nuclear Fuel Cycle Simulation System (VISTA) is a simulation system which estimates long term nuclear fuel cycle material and service requirements as well as the material arising from the operation of nuclear fuel cycle facilities and nuclear power reactors. It is a scenario based simulation tool which can model several nuclear fuel cycle options including existing nuclear power reactor types and future possible reactor types. The past operations of the power reactors and fuel cycle facilities can be modelled in the system, in order to estimate the current amount of spent fuel stored or total Pu in stored spent fuel. It can also accept future projections for nuclear power and other scenario parameters in order to predict future fuel cycle material requirements. The model has been designed to be an optimum mixture of simplicity, speed and accuracy. It does not require too many input parameters if the purpose is just to compare the requirements for selected scenarios. Furthermore, the accuracy of the system can be improved by introducing more detailed and correct sets of input parameters.--Publisher"s description.

    Edition Notes

    SeriesIAEA-TECDOC -- 1535.
    ContributionsInternational Atomic Energy Agency.
    The Physical Object
    Pagination95 p. :
    Number of Pages95
    ID Numbers
    Open LibraryOL16148131M
    ISBN 109201158068
    ISBN 109789201158062

    uranium raw material for the nuclear fuel cycle: exploration, mining, production, supply and demand, economics and environmental issues (uram) proceedings of an international symposium. Knowledge and Abilities Catalog for Nuclear Power Plant Operators: Pressurized Water Reactors (NUREG, Revision 2, Supplement 1) became effective for all examinations that are administered after Ap NUREG, Revision 3, was issued for public comment in April (comments were accepted until ).

      Liquid Fluoride Thorium Reactor (LFTR) is an innovative design for the thermal breeder reactor that has important potential benefits over the traditional reactor design. LFTR is fluoride based liquid fuel, that use the thorium dissolved in salt mixture of lithium fluoride and beryllium fluoride. Therefore, LFTR technology is fundamentally different from the solid fuel technology currently in by: 2. Analysis of proliferant country fuel cycle capabilities has been conducted for both plutonium and highly enriched uranium. State-of-the-art departmental counterproliferation experimental facilities range from nuclear radiation measurement laboratories using high-resolution detectors and imaging arrays to molecular spectroscopy laboratories.

    A nuclear reactor is a device in which nuclear chain reactions are initiated, controlled, and sustained at a steady rate (as opposed to a nuclear explosion, where the chain reaction occurs in a split second).Nuclear reactors are used for many purposes, but the most significant current uses are for the generation of electrical power and for the production of plutonium for use in nuclear weapons. Since the nuclear reactors based on the fission reaction are getting to be more economically competitive, with other type of electrical power plants such as gas or fossil fuel based.


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Nuclear fuel cycle simulation system (VISTA) Download PDF EPUB FB2

The Nuclear Fuel Cycle Information System (NFCIS) is an international directory of civilian nuclear fuel cycle facilities.

Its purpose is to provide the IAEA, its Member States and public users with current, consistent, and readily accessible information on existing, closed and planned nuclear fuel cycle facilities throughout the Size: 1MB.

Fuel Cycle Facilities - Fuel Incident Notification and Analysis System (FINAS) The FINAS is an international system through which participating countries exchange operating experience and lessons learned to improve the safety of nuclear fuel cycle system is jointly managed by the IAEA and the Nuclear Energy Agency of the Organization for Economic Cooperation and Development.

analysed how decisions made in one part of the nuclear fuel cycle may affect its back end. The meeting participants also identified processes and best practices for a holistic approach to the fuel cycle, with an emphasis on all potential impacts on spent fuel (re)processing, recycling, storage, transport and disposal.

Radioactive waste Management. Nuclear Physics Fundamentals and Applications. This note will focus on understanding the complete nuclear reactor system including the balance of plant, support systems and resulting interdependencies affecting the overall safety of the plant and regulatory oversight.

simulation of nuclear reactors core, fuel life control in light-water. Major topics covered includes: Special Relativity, Schroedinger's Wave Equation, Nuclear Models, Nuclear Decay Kinetics, Binary Nuclear Reactions, Fission and Fusion, Radiation, Nuclear Reactor Theory: Six Factor Formula, Reactor Design, Reactor Kinetics, Neutron Transport, Light Water Reactors, The Nuclear Fuel Cycle, Radiation Detection and.

The Untold Story of Nuclear. The United States and Canada released a new book at CEM under the NICE Future initiative called "Breakthroughs: Nuclear Innovation in a Clean Energy System." It’s a collection of short stories that focuses on near-term innovations in nuclear energy.

This is not a typical policy report. Nuclear Innovation: Clean Energy Future (NICE Future) is an international initiative of the Clean Energy Ministerial. NICE Future is led by the United States, Canada and Japan. Participating countries include Argentina, Poland, Romania, Russia, the United Arab Emirates, and the United Kingdom.

Conference: Proposed for presentation at the 8th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety (NUTHOS-8) held Octoberin Shanghai, China. Reprocessing and Recycling of Spent Nuclear Fuel presents an authoritative overview of spent fuel reprocessing, considering future prospects for advanced closed fuel cycles.

Part One introduces the recycling and reprocessing of spent nuclear fuel, reviewing past and current technologies, the possible implications of Generation IV nuclear.

large nuclear system analysis, modeling, and simulation project, including collection of engineering data, to assess alternative nuclear fuel cycle deployments relative to the four critical challenges; and halt development and demonstration of advanced fuel cycles or.

Haddal, Risa, Finch, Robert, and Cipiti, Benjamin B. Joint Fuel Cycle Study: Modeling and Simulation Process Monitoring and Containment and Surveillance and Safeguards Technology for Nuclear Material Accountancy. United States: N. p., Web. Information on nuclear energy and the nuclear fuel cycle from the World Nuclear Association.

World Nuclear Association Symposium will be held on September at Park Plaza Westminster Bridge, London, UK.

Early bird registration and call for presentations are currently open > The need for nuclear in a clean energy system. Capable of. Nuclear Engineering International, launched inis a monthly print magazine (about 44 pages/issue) including news, feature articles and technical articles of merit on the civil nuclear power industry, from front end fuel cycle to operations benchmarking (quarterly load factors league tables) to decommissioning & decontamination.

In India, nuclear power plants and all nuclear fuel-cycle facilities have been funded, developed, constructed, operated, and managed directly by the government or by public-sector enterprises under government control. The Integral Fast Reactor (IFR) is a fast reactor system developed at Argonne National Laboratory in the decade to The IFR project developed the technology for a complete system; the reactor, the entire fuel cycle, and the waste management technologies were all included in the development program.

The reactor concept had important features and characteristics that were completely. Worldwide R&D is underway to realize the closed fuel cycle as a sustainable energy supply system. Select 6 - Lead-cooled fast reactor. These lie in the nuclear fuel cycle rather than in the spread of nuclear power reactors.

It concludes that just as the Treaty, at its inception, reflected the political balance between the superpowers in the.

Nuclear Reactor Technology Development and Utilization presents the theory and principles of the most common advanced nuclear reactor systems and provides a context for the value and utilization of nuclear power in a variety of applications both inside and outside a traditional nuclear countries across the globe realize their plans for a sustainable energy future, the need for Book Edition: 1.

Finally, countries with long term policies to close the nuclear fuel cycle with the multi-recycling of nuclear materials are also maintaining efforts for the development of Gen-IV fast reactor designs (in particular Sodium Fast Reactors) and associated nuclear fuel cycle facilities.

A solution for the nuclear waste problem is the key challenge for an extensive use of nuclear reactors as a major carbon free, sustainable, and applied highly reliable energy source. Partitioning and Transmutation (P&T) promises a solution for improved waste management.

Current strategies rely on systems designed in the 60’s for the massive production of plutonium. We propose an innovative Cited by: 4.

The publications in the IAEANuclear Energy Series provide information in the areas of nuclear power, nuclear fuel cycle, radioactive waste management and decommissioning, and on general issues that are relevant to all of the above mentioned areas.

The structure of the IAEA Nuclear Energy Series comprises three levels: 1 — Basic Principles and. describes the process of fabricating, using, and disposing of the nuclear fuel, which is a process known as the nuclear fuel cycle.

Section three gives a description of the nuclear reactors that are currently operating both in the U.S. and around the world, a description of the newFile Size: 1MB. The parallel highly innovative simulation INL code system (PHISICS) toolkit (Rabiti et al.,“New Simulation Schemes and Capabilities for the PHISICS/RELAPD Coupled Suite,” Nucl.

Sci. Eng., (1), pp. –; Alfonsi et al.,“PHISICS Toolkit: Multi-Reactor Transmutation Analysis Utility—MRTAU,” PHYSOR Advances Author: Andrea Alfonsi, George L Mesina, Angelo Zoino, Nolan Anderson, Cristian Rabiti.His research has focused on the physics and engineering analysis of nuclear systems, including space-time reactor kinetics, optimization of nuclear fuel cycles, transmutation of spent nuclear fuel, risk and safety analysis of nuclear systems, power plant simulation and control, advanced reactor design and analysis, and coupled multiphysics.