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2 edition of compendium of computer codes for the safety analysis of fast breeder reactors found in the catalog.

compendium of computer codes for the safety analysis of fast breeder reactors

United States. Dept. of Energy. Division of Reactor Research and Demonstration

compendium of computer codes for the safety analysis of fast breeder reactors

by United States. Dept. of Energy. Division of Reactor Research and Demonstration

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  • 17 Currently reading

Published by Dept. of Energy, Division of Reactor Research and Development, for sale by the National Technical Information Service in [Washington], Springfield, Va .
Written in English

    Subjects:
  • Liquid metal fast breeder reactors,
  • Breeder reactors,
  • Nuclear reactors -- Computer programs

  • Edition Notes

    SeriesDOE/ET-0009
    The Physical Object
    Pagination[1], 431 p. ;
    Number of Pages431
    ID Numbers
    Open LibraryOL14862305M

    Thorium-fueled fast reactors breed large quantities of U, which can be employed in advanced reactors and thermal reactors moderated by water and heavy water to increase fuel utilization by ≈20%; thereby extracting a greater amount of energy per mined ton of uranium ore. This paper summarizes the results from the level-1 Probabilistic Safety Analysis of Prototype Fast Breeder Reactor (PFBR) which is under construction at Kalpakkam. The scope of this study is limited to internal events at full power. The regulatory requirement in India is risk informed and the required target value for overall core damage frequency (CDF) <; le-6 / ry.

    The conventional fast reactors built so far are generally fast breeder reactors (FBRs) implying a net increase in Pu from breeding, due to a conversion ratio above These have a 'fertile blanket' of depleted uranium (U) around the core, and this is where much of the Pu is produced. Studies have been made on the costs of various designs of IH X for large commercial fast breeder reactors such as the PLBR. Beyond the obvious economies of scale, it is expected that further design simplification such as described above will reduce overall IHX costs by up to 50% as compared with direct extrapolation of the original FFT F designs.

      Compendium of Post Accident Heat Removal Models for Liquid Metal Cooled Fast Breeder Reactors (European Appl. Res. Rept. Nucl. Sci. Technol. Vol.6, No.) [B. D. Turland] on *FREE* shipping on qualifying offers. Development and Validation of the ECART Code for the Safety Analysis of Nuclear Installations. F Analysis of Sodium Fire in the Containment Building of Prototype Fast Breeder Reactor Under the Scenario of Core Disruptive Accident. P. M An Integration of the Restructured MELCOR for the MIDAS Computer Code. Sunhee Park, Dong Ha.


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Compendium of computer codes for the safety analysis of fast breeder reactors by United States. Dept. of Energy. Division of Reactor Research and Demonstration Download PDF EPUB FB2

Get this from a library. A compendium of computer codes for the safety analysis of fast breeder reactors. [United States. Department of Energy. Division of Reactor Research and Demonstration.].

Comprised of six chapters, this book opens with an overview of methods used to evaluate nuclear safety, along with neutron kinetics, thermal and feedback effects, and fault tree analysis. The reader is then introduced to possible system disturbances in relation to three distinct fast reactor systems: liquid-metal-cooled fast breeder reactors.

Comprised of six chapters, this book opens with an overview of methods used to evaluate nuclear safety, along with neutron kinetics, thermal and feedback effects, and fault tree analysis. The reader is then introduced to possible system disturbances in relation to three distinct fast reactor systems: liquid-metal-cooled fast breeder reactors Book Edition: 1.

This book is a complete update of the classic FAST BREEDER REACTORS textbook authored by Alan E. Waltar and Albert B. Reynolds, which, along with the Russian translation, served as a major Author: Staffan Qvist.

Purchase Fast Breeder Reactors - 1st Edition. Print Book & E-Book. ISBNBook Edition: 1. Central to achieving breeder capability is the reactor itself. Full understanding of material and fuel performance in the special environment of the reactor core is vital to the success of any reactor system.

The fast breeder reactors have a particularly difficult problem resulting from damaging effects of fast neutron irradiation on. View Fast Breeder Reactor PPTs online, safely and virus-free. Many are downloadable. Learn new and interesting things. Get ideas for your own presentations. Share yours for free.

The computer code ANFIBE correlates well the data on swelling and tritium release available and is able to extrapolate these data to the DEMO conditions. However, more data are required from high temperature irradiation at high fluence in fast reactors.

Capsules containing many beryllium samples irradiated in the U.S. fast reactors FFTF and EBR. The potential for sodium release to reactor containment building from reactor assembly during Core Disruptive Accident (CDA) in Fast Breeder Reactors (FBR) is an important safety issue with reference to the structural integrity of Reactor Containment Building (RCB).

Fast reactors can radically extend the world’s uranium resources. In a fast breeder reactor, extra U– is added so that more fissile atoms are created than are destroyed by fission. The additional neutrons from fast fissions make this possible.

This means that essentially all of the original uranium ore (which is % U and % U. Book series; Subjects.

All Subjects Fractional Release (X) determined from RIBID code (ref.9) ^Assuming 40% sodium flow through filter II Nuclear Technology 46 2 November 9 U.S. Department of Energy A compendium of Computer Codes for the Safety Analysis of Fast Breeder Reactors DOE/ET Sodium Fast Reactors with Closed Fuel Cycle delivers a detailed discussion of an important technology that is being harnessed for commercial energy production in many parts of the world.

Presenting the state of the art of sodium-cooled fast reactors with closed fuel cycles, this book: Offers in-depth coverage of reactor physics, materials, design, safety analysis, validations, engineering.

selection and development of computer codes that may be used to analyze non-LWRs. One of the primary objectives of Strategy 2 of the Implementation Action Plan (IAP) for non-LWRs is the development of codes suitable for safety analysis of gas-cooled reactors, sodium fast reactors, molten salt reactors, and “micro” reactors.

Topics: Computer simulation, Safety, Scram, Sodium fast reactors, Accidents, China, Displacement, Fast neutron reactors, Flow (Dynamics), Pipes The Choose of Decay Heat Removal Systems of SFR. The safety design concept of LMFBRs follows the same basic principles (multiple barrier concept and four level safety concept) as they were developed for light water reactors.

This holds despite of the fact that LMFBRs have different design characteristics (fast neutron spectrum, liquid metal as coolant, plutonium-uranium fuel). 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. The second half of the book deals with the two main topics of interest related to operating reactors – reactor kinetics/dynamics, and in-core fuel management.

Additional chapters have been added to expand and bring the material up-to-date and include the utilization of more computer codes. The knowledge of the decay heat of nuclear fuel is necessary for performing the reactor safety analysis. In this study, analysis of the radioactivity, decay heat and the isotopic mass variation.

@article{osti_, title = {Recommended practices in elevated temperature design: A compendium of breeder reactor experiences (): An overview}, author = {Wei, B C and Cooper, Jr, W L and Dhalla, A K}, abstractNote = {Significant experiences have been accumulated in the establishment of design methods and criteria applicable to the design of Liquid Metal Fast Breeder Reactor (LMFBR.

Status of safety technology for radiological consequence assessment of postulated accidents in liquid metal fast breeder reactors, Canoga Park, California, 29 July July United States: N. p. The safety section includes both traditional safety analysis techniques as well as a perspective on methods to achieve passive safety response.

Whereas the bulk of the book is focused on sodium-cooled fast spectrum systems, a final section features gas-cooled and lead-cooled fast reactor s: 1.Evaluation of Hydrogen Transport Behavior in the Power Rising Test of Japanese Prototype Fast Breeder Reactor Monju.

View Article. PDF. Topics: Breeder reactors, Engineering prototypes, Hydrogen, Boilers, Temperature, Coolants, Heat transfer, Light water The Validation of the 4S Safety Analysis Code for Loss of Offsite Power. Fast breeder reactors are the least safe Maam IST SA Aiyar in Swaminomics | India | TOI Nuclear safety has become a top .