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3 edition of Revised uranium-plutonium cycle PWR and BWR models for the origen computer code found in the catalog.

Revised uranium-plutonium cycle PWR and BWR models for the origen computer code

Oak Ridge National Laboratory. Chemical Technology Division

Revised uranium-plutonium cycle PWR and BWR models for the origen computer code

by Oak Ridge National Laboratory. Chemical Technology Division

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  • 39 Currently reading

Published by Dept. of Energy, Office of Technology, Oak Ridge National Laboratory, Chemical Technlogy Division, for sale by the National Technical Information Service in Oak Ridge, Tenn, Springfield, Va .
Written in English

    Subjects:
  • Nuclear reactors -- Computer programs.

  • Edition Notes

    StatementA. G. Croff ... [et al.]. Oak Ridge National Laboratory, Chemical Technology Division.
    SeriesORNL/TM ; 6051, ORNL/TM -- 6051.
    ContributionsCroff, A. G.
    The Physical Object
    Paginationix, 127 p. :
    Number of Pages127
    ID Numbers
    Open LibraryOL18014296M

    Hence, High Enriched Uranium (HEU) and Low Enriched Uranium (LEU), UraniumThorium (U, Th), Uranium-Plutonium (U-Pu), and Plutonium (Pu) fuel cycles have been employed in various applications. Until the s, two types of fuel designs were used extensively, namely, bi-isotropic (BISO) and tri-isotropic (TRISO) particles as shown in Fig. 5. CORE NEUTRONICS, THERMAL HYDRAULICS AND FUEL CYCLE The equilibrium fuel salt composition was obtained with the help of MCNP-4B+ORIGEN code (with library received on the basis of ENDF/B-V,VI.

    7/17/ AM. Page vii. Forward and Acknowledgments. We decided to study the future of nuclear power because we believe this technology, despite the challenges it faces, is. Nuclear Safeguards, Security, and Nonproliferation: Achieving Security with Technology and Policy was inspired in part by a previous study by Carter, Steinbruner, and Zraket that focused on the organizational requirements for safely maintaining a nuclear arsenal during the Cold War era.1 Their book, Managing Nuclear Operations, is still an.


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Revised uranium-plutonium cycle PWR and BWR models for the origen computer code by Oak Ridge National Laboratory. Chemical Technology Division Download PDF EPUB FB2

@article{osti_, title = {Revised uranium--plutonium cycle PWR and BWR models for the ORIGEN computer code}, author = {Croff, A. and Bjerke, M. and Morrison, G. and Petrie, L. M.}, abstractNote = {Reactor physics calculations and literature searches have been conducted, leading to the creation of revised enriched-uranium and.

Get this from a library. Revised uranium-plutonium cycle PWR and BWR models for the origen computer code. [A G Croff; Oak Ridge National Laboratory. Chemical Technology Division.]. The ORIGEN isotope generation and depletion computer code was employed tomore» These results have been compared with similar calculations using enriched-uranium model reactors to provide data that have been used in the GESMO Study for comparison of the potential environmental hazards of enriched-uranium reactors with those of plutonium.

Croff AG, Bjerke MA, Morrison GW, Petrie LM () Revised uranium-plutonium cycle pwr and bwr models for the ORIGEN computer code. Tech. Rep. ORNL/TM. Reactor physics calculations have led to the development of nine liquid-metal fast breeder reactor (LMFBR) models for the ORIGEN2 computer code.

Four of the models. Methods of detection unique to arms control and treaty verification are discussed here. The conditions and opportunities for detection in these enivronments are contrasted with portal monitoring and cargo screening environments.

First, neutron multiplicity counting is covered, including both the technology involved and the mathematics : Edward C. Morse. Detector response to neutrons and photons is described for pressurized-water-reactor (PWR) and boiling-water-reactor (BWR) systems.

Particle fluxes are calculated, and detector signals are then. Advanced Fuel Cycle Cost Basis – Edition vi Septem NTRD-FCO (September ) vi Advanced Fuel Cycle Cost Basis New data and the references supporting it in the cost modules Additional reactor types (R-modules) Additional sub-modules that address different topics within the main module (e.g.

fabrication of different types of fuels). Light water reactor spent fuel in the U.S. contains only about 37 MBq of carbon per kg U (1 curie per metric tonne of initial uranium); however, the potential U.S.

repository at Yucca Mountain would be located above the water table, where air is by: 5. The safe, secure, reliable and economic management of spent fuel arising from nuclear power reactors is key for the sustainable utilization of nuclear energy and covers many technological aspects related to the storage, transportation, recycling and disposal of the spent fuel and the high level waste (HLW) generated from spent fuel reprocessing.

The sustainability of nuclear energy involves. IAEA-TECDOC Emerging nuclear energy and transmutation systems: Core physics and engineering aspects August The originating Section of this publication in the IAEA was: Nuclear Power Technology Development Section International Atomic Energy Agency Wagramer Strasse 5 P.O.

Box A Vienna, Austria. IAEA-TECDOC Thorium fuel utilization: Options and trends Proceedings of three IAEA meetings held in Vienna inand November The originating Section of this publication in the IAEA was: Nuclear Power Technology Development Section International Atomic Energy IAEA Wagramer Strasse 5 P.O.

Box A Vienna, Austria THORIUM FUEL UTILIZATION: OPTIONS AND 5/5(3). cycle models that could be used for cost analysis is provided.

Section 7 summarizes the conclusions and recommendations resulting from the development of the report. Section 8 provides general (nonmodule specific) report references. The appendix provides additional fuel cycle cost details on the code File Size: 11MB. jaeri-conf proceedings of the second workshop on residual radioactivity and recycling criteria jointly sponsored by the united states environmental protection agency the office of radiation and indoor air, and the japan atomic energy research institute novembertokai, japan july (eds.) hideaki yamamoto and john a.

mackinney* japan atomic energy research institute. International Conference on Advances in Nuclear Forensics — Countering the Evolving Threat of Nuclear and Other Radioactive Material out of Regulatory Control — Background: Nuclear forensics is an essential component of national nuclear security infrastructure which can help to address the threat of nuclear and other radioactive material that is out of regulatory control as well as to.

Full text of "Analytical methods for safeguards and accountability measurements of special nuclear materials" See other formats. a solute in a solvent depends on the in trinsic mass transfer coefficient k s1 the surface area S, and the driving force of concentration difference (C eq C) as shown below:)(1 teq sCCSkR () where C t is the ion concentration in solution at time t Kinetics models The kinetics for dissolution of metal oxides in the acidic media can.

Introduction Phenomena Experimental Programmes Bottom Reflood Models 1 Lumped Parameter Models 1 Quenching Models 1 Models for Fluidisation 1 More Sophisticated Models Top Reflood Models 1 Critical Heat Flux Models 1 Upper Bed Quenching Rate Limitation Models 1 Quench Front Limitation Models.

Safety and Regulatory Issues of the Thorium Fuel Cycle. SciTech Connect. Ade, Brian; Worrall, Andrew; Powers, Jeffrey. Thorium has been widely considered an alternative to uranium fuel because of its relatively large natural abundance and its ability to breed fissile fuel (U) from natural thorium (Th).

Possible scenarios for using thorium in the nuclear fuel cycle include. The Oak Ridge National Laboratory computer code, ORIGEN (CCC, ), was used to obtain the elemental composition of irradiated low-enriched uranium (LEU)/mixed-oxide (MOX) pressurized-water reactor fuel assemblies.

Described in this report are the input parameters for the ORIGEN calculations. Full text of "Monthly catalog of United States government publications" See other formats.ML Fuel Qualification Plan - Free ebook download as PDF File .pdf), Text File .txt) or read book online for free.

The U.S. Department of Energy (DOE) has contracted with Duke COGEMA Stone & Webster (DCS) to qualify mixed oxide (MOX) fuel for disposition of surplus weaponsgrade (WG) .Nuclear health Risks - Free download as PDF File .pdf), Text File .txt) or read online for free.5/5(1).