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Friday, July 31, 2020 | History

2 edition of Analysis of fission-product effects in a fast mixed-spectrum reactor concept found in the catalog.

Analysis of fission-product effects in a fast mixed-spectrum reactor concept

J. R. White

Analysis of fission-product effects in a fast mixed-spectrum reactor concept

by J. R. White

  • 87 Want to read
  • 12 Currently reading

Published by Dept. of Energy, Oak Ridge National Laboratory, for sale by the National Technical Information Service] in Oak Ridge, Tenn, [Springfield, Va .
Written in English

    Subjects:
  • Nuclear fission -- By-products.,
  • Fast reactors.,
  • Breeder reactors.

  • Edition Notes

    StatementJ. R. White, Computer Sciences Divsion, T. J. Burns.
    SeriesORNL/TM ; 7091, ORNL/TM -- 7091.
    ContributionsBurns, T. J. 1946-, Union Carbide Corporation. Computer Sciences Division., Oak Ridge National Laboratory.
    The Physical Object
    Paginationvi, 29 p. :
    Number of Pages29
    ID Numbers
    Open LibraryOL18017579M

    The comparative analysis using a consistent set of transmutation strategies is addressed in Chapter 3. The status of FR and ADS technologies is compared in Chapter 4; Chapter 5 analyses the safety aspects of both systems. The report addresses the economics of transmutation strategies in Chapter 6, the perceived R&D needs in Chapter 7 and. New Boiling Salt Fast Breeder Reactor Concepts NA Fuel Properties and Nuclear Performance of Fast Reactors Fueled with Molten Chlorides NSE Fission Product Effects in Molten Chloride Fast-Reactor Fuels ANL Molten-Salt Fast Reactors ORNL-CF Fused Salt Fast Breeder MIT

    nuclear reactor engineering Download nuclear reactor engineering or read online books in PDF, EPUB, Tuebl, and Mobi Format. Click Download or Read Online button to get nuclear reactor engineering book now. This site is like a library, Use search box in the widget to get ebook that you want. Nuclear Reactor Engineering Principle And Concepts. J. R. White and T. J. Burns, "Preliminary Evaluation of Alternate Fueled Gas Cooled Fast Reactors," Oak Ridge National Laboratory, ORNL/TM (Dec. ). J. R. White and D. T. Ingersoll, "Analysis of the Thorium Axial Blanket Experiments in the PROTEUS Reactor," Oak Ridge National Laboratory, ORNL/TM (Dec. ).

    The energy trilemma and UN SDG 7 form the key drivers for the future of all kinds of energy research. In nuclear technology, molten salt reactors are an interesting option, since they can offer a game-changing approach to deliver an attractive, highly sustainable option for a zero-carbon society by providing sufficient breeding for a self-sustained long-term operation based . Fission product, in physics, any of the lighter atomic nuclei formed by splitting heavier nuclei (nuclear fission), including both the primary nuclei directly produced (fission fragments) and the nuclei subsequently generated by their radioactive fission fragments are highly unstable because of their abnormally large number of neutrons compared with protons; .


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Analysis of fission-product effects in a fast mixed-spectrum reactor concept by J. R. White Download PDF EPUB FB2

Get this from a library. Analysis of fission-product effects in a fast mixed-spectrum reactor concept. [J R White; T J Burns; Union Carbide Corporation.

Computer Sciences Division.; Oak Ridge National Laboratory.]. Fission-Product Effects in Molten Chloride Fast-Reactor Fuels* The use of the molten chlorides as fast-reactor fuels has been given consideration in the past; recently, a mobile-fuel fast reactor has been proposed4 consisting of 30 to 50 mole% (Pu, U)Cl 3 dissolved in a molten mixture of NaCl and KCl, which is to be contained inFile Size: KB.

Referred to as the Long-Lived Reactor (LLR) in this study, the concept is a sodium-cooled, single-spectrum (fast) design, that is fueled with low-enriched uranium (LEU) and can operate continuously for several by: 1. Los Alamos conducted a dual fission‐chamber experiment in the s in the Bigten critical assembly to determine fission product data in a fast (fission neutron spectrum) environment, and this defined the Laboratory’s fission basis today.

We describe how the data from this experiment are consistent with other benchmark fission product yield measurements 97Zr, Ba, Cited by: 3. In this paper, we analyze an innovative fast reactor concept developed within the CP-ESFR European project [] focusing on phenomena affecting the initiation and the transition (to full core melting) phases of an accident due to unprotected loss of coolant flow (ULOF).The experience gained in the past by numerous in-pile and out-pile experiments performed, e.g., [12,13], has Cited by: 4.

The calculation of the spent-fuel composition is the baseline problem of the analysis of the nuclear and radiological safety of objects with spent fuel assemblies.

The use of fission product libraries formed on the basis of evaluated nuclear data with an enlarged number of energy points is especially important for high-precision calculations of the nuclide composition Cited by: 1. Abstract. Transmutation of long-lived fission products (LLFPs: 79 Se, 93 Zr, 99 Tc, Pd, I, and Cs) into short-lived or non-radioactive nuclides by fast neutron spectrum reactors without isotope separation has been proposed as a solution to the problem of radioactive wastes by: 6.

Analysis of Fission Products-A Method for Verification of a CTBT During On-Site Inspections Li, Bino If under a Comprehensive Test Ban Treaty a suspicious event can be accurately located, it should be possible to sample possible fission products through an on-site inspection.

A Physical Description of Fission Product Behavior in Fuels for Advanced Power Reactors ANL/24 by G. Kagana Florida International Univeristy J. Rest Nuclear Engineering Division, Argonne National Laboratory September 4, Cited by: 4. The calculation of the composition of irradiated fuel for different degrees of burnup is a basic problem in the analysis of nuclear-radiological safety of objects holding spent fuel assemblies.

The yield of fission products is one of the important initial indicators in burnup calculations. Methods for compiling libraries of fission products yield on the basis of the Cited by: 5. A fission product of secondary importance is samarium with σ a = 41, b. These nuclei act as poisons in the reactor, thereby reducing the core multiplication factor.

Fission product poisoning transpires over a longer period (~ hours) compared to the fuel and moderator temperature effects.

White and T. Burns, "Analysis of Fission-Product Effects in a Fast Mixed-Spectrum Reactor Concept," Oak Ridge National Laboratory, ORNL/TM (Feb.

- J. White, D. Ingersoll, U. Schmocker, and K. Gmur, "Analysis of a Swiss Thorium Blanket Integral Experiment," International Conf. on Nuclear Cross Sections for. Thermal-Hydraulic Analysis of Nuclear Reactors. there appears to be nearly unlimited supply of fission product fuel, providing the new generation (i.e., GEN IV) concepts are developing over Author: Bahman Zohuri.

A brief summary of a method to produce fission product Mo without the need for a nuclear reactor. Slideshare uses cookies to improve functionality and performance, and to provide you with relevant advertising.

Safety analysis for small long life fast CANDLE reactor was performed with ULOF (unprotected loss of flow), SDRW (unprotected shut down rods withdrawal), ULOHS (unprotected loss. Fission Product Processes In Reactor Accidents - CRC Press Book The Three Mile Island and Chernobyl nuclear incidents emphasized the need for the world-wide nuclear community to cooperate further and exchange the results of research in this.

A fast-neutron reactor or simply a fast reactor is a category of nuclear reactor in which the fission chain reaction is sustained by fast neutrons, as opposed to thermal neutrons used in thermal-neutron reactors.

Such a reactor needs no neutron moderator, but requires fuel that is relatively rich in fissile material when compared to that required for a thermal-neutron reactor.

onted with the data that you can’t get enough neutrons from a thermal-spectrum reactor to “burn” U, they began to investigate what happens if you use a “fast-spectrum” reactor.

At “fast” energies (the energies on the right-hand side of the plot) things start to look a lot better for plutonium.

Fast Fission Factor. The first process that the fission neutrons of one neutron generation may undergo is the fast process of fast fission occur at higher than thermal energies, in fact mainly at energies higher than 1 fast fission occurs mainly in U, but also in other fissile isotopes ( U and Pu).The fission cross-section of U is similar to the.

Equations for the fission-product numbers and activities in a circulating fuel were derived from equations existing in the literature for the growth and decay of fission products resulting from one reactor operation and shutdown cycle. lived fission products by neutron bombardment.

From this standpoint, a nuclear reactor provides the obvious means for transmutation of MA nuclides. Among the various nuclear reactors, a fast reactor is considered to have the greatest potential to transmute MA effectively, because of its hard neutron spectrum [].File Size: KB.INTRODUCTION TO NUCLEAR REACTOR PHYSICS is the most comprehensive, modern and readable textbook for this course/module.

It explains reactors, fuel cycles, radioisotopes, radioactive materials, design, and operation. Chain reaction and fission reactor concepts are presented, plus advanced coverage including neutron diffusion theory.Trace Fission Product Ratios 51 of isotopic ratios of these noble fission gases could thus be used to ver-ify operator declarations or determine fuel parameters such as fuel type, burn-up, and reactor type.

The calculated database of xenon and krypton iso-topic ratios was created using a series of reactor analysis codes to model es-Cited by: